JAER1-M—93-080

.TP931JQ49

J A E R I - M 93-080

JAERI FUEL CLEANUP SYSTEM (J-FCU)

STAND-ALONE TRITIUM TEST AT THE TSTA

—FIRST J-FCU TEST WITH ONE GRAM

OF TRITIUM ON J U N E 1991 —

March 1993

Satoshi KONISHI, Takumi HAYASHI, Masahiko INOUE*1

Kazuhiro HIRATA*2, Kenji OKUNO, Yuji NARUSE

J.W.BARNES* 3, W.HARBIN*3, J.R.BARTLIT* 3

and J.L.ANDERSON* 3

Japan Atomic Energy Research Institute

~AERI-M

93-080

~AERI FUEL CLEANUP SYSTEM (~-FCU)

STAND-ALONE TRITIUM TEST AT THE TSTA

-FIRST .J-FCU TEST WITH ONE GRAM

OF TRITIUM ON .JUNE 1991-

March 1993

.TAER:-U-93-080

思 9311049

Satoshi KONISHI. Takumi HAY ASHI. Masahiko INOUE・1Kazuhiro HIRATA時. Kenji OKUNO. Yuji NARUSE

J.W.BARNES*:¥ W.HARBINぺJ.R.BARTLIT叫

and J.L.ANDERSON時

日 本原子力 研究所

Ja，仰nAfomic Energy Research Institute

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JAERI-M reports are issued irregularly. Inquiries about availability of the reports should be addressed to Information Division, Department

of Technical Information. Japan Atomic Energy Research Institute. Tokai-mura. Xaka gun. Ibaraki ken 319 11. Japan.

© Japan Atomic Energy Research Institute. 1993

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あて.お 111しニ Lくた'きい なお.このほかにP.tl吋法人f車、 f・1J弘済会資料センター(〒:H9-11茨域

県倒:Jal郡東海村日本版 U)研究，i，庁内)で惚'ゲによる実'lhfi衡をおこなうてjjリます

JAERI -¥1 reports are Issued Irregularly

lnqumes about 出品Ilablhtyof the reports sho叫dbe addre話edto Information 0I'>151on. Departrnent

of Techmcal lnformation. ]apan Atomlc Energy Research Insutute. Tokat-mura.、;aka-gun.

lbarakl ken 31911. japan

。japanAtomic Energy Research 1nstttute. 1993

編集厳~h 日本原 f-jH庁 究所

印 刷 u-，!:，f;j速印刷株式会社

JAERI-M 93-080

JAERI Fuel Cleanup System (J-FCU) Stand-alone Tritium Test at the TSTA

- First J-FCU test with one gram of tritium on June 1991 -

*1 Satoshi KONISHI, Takumi HAYASHI, Masahiko INOUE Kazuhiro HIRATA , Kenji 0K0N0, Yuji NAROSE J.W.BARNES*3, W.HARBIN*3, J.R.BARTLIT*3

and J.L.ANDERSON*3

Department of Fusion Engineering Research Naka Fusion Research Establishment

Japan Atomic Energy Research Institute Naka-machi, Naka-gun, Ibaraki-ken

(Received March 8, 1993)

JAERI designed, fabricated, and installed the JAERI Fuel Cleanup System (J-FCU) as a subsystem of simulated fusion fuel loop at the TSTA. The main function of the J-FCU is to purify and to recover hydrogen isotopes from simulated plasma exhaust while exhausting tritium free impurities.

After a lot of deuterium tests, a first tritium test of the J-FCU was performed with one gram of tritium at the TSTA on June 1991. Main purpose of this test was to evaluate the total integrity and function of the J-FCU system with a DT mixture. Through this test, the J-FCU was operated well and its function with tritium was demonstrated.

*1 Mitsubishi Heavy Industries, Ltd. *2 Sumitomo Heavy Industries, Ltd. *3 Los Alamos National Laboratory

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JAERI-M 93-080

JAERI Fue1 C1eanup System (J-FCU) Stand-a1one

Tritium Test at the TSTA

-First J-FCU test with one gram of

tritium on June 1991 -

士官

Satoshi KONISHI， Takumi HAYASHI， Masahiko INOUE ~ 古ワ

Kazuhiro HlRATA - Kenji OKUNO， Yuji NARUSE 宏司 *'l. 会1

J.W.BARNES -， W.HARBIN -， J.R.BARTLIT -士官

and J.L.ANDERSON -

Department of Fusion Engineering Research

Naka Fusion Research Estab1ish田ent

Japan Atomic Energy Research Institute

Naka-machi， Naka-gun， Ibaraki-ken

(Received March 8， 1993)

JAERI designed， fabricat~d ， and insta11ed the JAERI Fue1 C1eanup

System (J-FCU) as a subsystem of simulated fusion fuel loop at the TSTA.

百lem品infunction of the J-FCU is to purify and to recover hydrogen

isotopes from simu1ated plasma exhaust while e~，austing tritium free

impurities.

After a 10t of deuterium tests， a first tritium test of the J-FCU

was performed with one gram of tritium at the TSTA on June 1991. Main

purpose of this test was to evaluate the total integrity and function of

the J-FCU system with a DT mixture. Through this test， the J-FCU was

operated well and its function with tritium was demonstrated.

士1 Mitsubishi Heavy Industries， Ltd.

*2 Sumitomo Heavy Industries， Ltd.

犬3 Los A1amos National Laboratory

(1)

JAERI-M 93-080

This report describes the detail test results of the J-FCU first tritium test and discuss its functions by stand-alone mode. Residual tritium inventory of the J-FCU system was also discussed.

Keywords : Fusion, Fusion Fuel Cycle, Tritium, Fuel Cleanup, TSTA, Palladium Diffuser, Ceramic Electrolysis Cell, J-FCU, Tritium Inventory

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JAE.悶ーM 93-080

This report describes the detail test results of the J-FCU first

tritium test and discuss its functions by stand-alone mode. Residual

tritium inventory of the J-FCU system was also discussed.

Keywords Fusion， Fusion Fuel Cycle. Tτitium. Fuel Cleanup， TSTA.

Palladium Diffuser. Ceramic Electrolysis Cell. J-FCU. Tritium

Inventory

(2)

JAERI-M 93-080

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J.R.BARTLIT'3 • J.L.ANDERSON*3

(1993*P3J3 8 B g S )

m.mteBKfefa&mflW.llW.fe Annex IV K * - ^ * , *ff ln x T 7 t x i i f f t R l i O h V

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JAERI-M 93-080

J -FCU (JAERI一燃料精製捕集実験装置)

のTSTAにおける単独トリチウム試験

-Igのトリチウムを用いた初のJ-FCU

単独トリチウム試験結果(1991年6月)一

日本原子力研究所那同研究所核融合工学部

小西哲之・林 巧・井上雅彦.I・平田一弘・2

奥野健二・成瀬雄二・ J.W.BARNES.3• W.HARBIN*3

J .R.BARTLIT・3 • J .L.ANDERSON03

(1993年3月8日受理}

原研は日米核融合研究協力協定AnnexlVに基づき，米国ロスアラモス国立研究所のトリ

チウムシステム試験施設 (TSTA)において核融合炉燃料ループの実証試験を行っている。

J -FCU (JAERI一燃料精製捕集実験装置)は. TSTAのメインサプシステムとして，原

研が設計，製作し. 1990年に TSTAに据え付けたものである。その機能は，模擬プラズマ

排ガス中の水素同位体を精製捕集しトリチウムを含まない不純物のみを排出することにあ

る。

約 l年の重水素実験の後. 1991年6月に 1グラムのトリチウムを用いた初めてのJ-FCU

単独トリチウム試験がおこなわれ，その単体性能がトリチウムで実証された。

本報告書は，上記試験の概要と詳細結果をまとめたものである。また，実験後のJ-FCU

の残留トリチウムインベントリーについても議論する。

那珂研究所:干 311-01茨城県那珂郡那珂町大字向山801-1

* 1三菱重工業側

* 2住友重機械工業側

*3ロスアラモス国立研究所

JAERI-M 93-080

Contents

I. Introduction 1 A. Plan for the JAERI Fuel Cleanup System Stand alone Tritium Test 2 1. Purpose 2 2. Configuration 2 3. Subsystem Required 2 4. Personnel 3 5. Time 3 6. Possible Hazards 3 7. Outline 4 8. Data 7

M. Results for the J-FCU Stand alone Tritium Test 13 1. Summary 13 2. Purpose 14 3. Configuration 14 4. Operations 15 4.1 Preparations 15 4.2 Ig Tritium Supply 15 4.3 Non-impurity Operation 15 4.4 Impurity Operation 15 4.5 Tritium Recovery 16 4.6 Inventory Check 16

5. Results 17 5.1 Palladium Diffuser 17 5.2 Catalytic Reactor 17 5.3 Cold Traps 17 5.4 Ceramic Electrolysis Cell 18 5.5 Gaschromatographs 18 5.6 Zirconium Cobalt Bed 18 5.7 Total Performance 18 5.8 Inventory 19 5.9 Further Subjects 19

References 24 Attachments 25

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JAERI-M 93-080

Contents

工ntroduction ••••...•••.•..•..•..•••••••••.••••••..••..••.••.••.••••• 1

n. P1an for the JAERI Fue1 C1eanup System Stand a10ne Tritium Test ••••• 2

1. Purpose •.•.••..•.•••.•••••.••.•••••••••••..•••.•..•••••.•..•••••.• 2

2. Configuration •..••.••..•••..•••••••.•••••.••••.•.•••••.••.•••••••• 2

3. Subsystem Required •.•••••••.•••••••••••••••••••.•••••••••••••.•••• 2

4. Personne1 •.••••.••••••••••.•••••••••••.••••••••••••.•••••••.•••••• 3

5. Time •••...•..•••••••.•.•••..••..•.•.•••••••••...•••...••••.••••••. 3

6. Possib1e Hazards ••••.•••••.•••••.•••••••••••••••••••••••..•••••.•. 3

7. Out1ine ••••..•..••.•••••...•••••.••.••.•••••••••••...•••.•..•••••• 4

8. Da ta ..••.•••.••.•••..••....••....•••...••••....•.•...•....••.•..•• 7

m. Resu1ts for the J-FCU Stand a10ne Tritium Test ••••••••••.•.•••.••••• 13

1. Summary. • . . • • . . . • • . • . • • . • • • • • • . • • . • • . . • • • . • . • • • . • • . • • • • • • • • • • . . • • • 13

2. Purpose. • • . . . • • • • • • • • • . . . • • . . . • • • . . . . • . . • • • . • • . . . • • • . • • • • . • . • • • • • . 14

3. Configuration. . . . • . . • • • • • • • • • . . • • • . • • • • • • • • . • • . . . • • • • • . • • • • • . • . • • • 14

4. Operations. • . • . • • . • • • . . . • • • • • . • • • . • • • . • . • • • • • • . . • • • • • • • • • • • • . • • • • • 15

4.1 Prepara tions •.••••....•••.•.••••.•••..•••.....•••.••••••••••.•• 15

4.2 19 Tritium Supp1y ....•••••.••••••••••••••..•.•••••••.••..•.•••• 15

4.3 Non-impurity Operation ••....••••..••..•.•••.•••••.•••••.••••••• 15

4.4 工mpurityOperation .•..••••.••..••.••....••....••.•••••...•••..• 15

4.5 Tritium Recovery ••..•••..•.•••..••.•..•....••••••••••••..••.••• 16

4.6 Inventory Check •.•••••..•••.••..•••..••••••.•••...••••••.•••.•. 16

5 . Resu1 ts •..•••..•••....•..•••.•.•..•••..•.••.•..•....•••.•.•••.••.• 17

5.1 Pa11adium Diffuser .....................................市・・・・・・・ 17

5.2 Cata1ytic Reactor ••.•..••.•.•••••••.••••••••••••..•••..••••..•. 17

5.3 Co1d Traps .•...••.••..••••••...•.••..••..••••.••.••••.••.•.•••• 17

5.4 Ceramic E1ectro1ysis Ce11 ••.•..•.•.••••.••.••.••••••.•.•...•••• 18

5.5 Gaschromatographs.............................................. 18

5.6 Zirconium Coba1t Bed ••.••••.••..•..••••.•.•.•••..•...••.••..•.• 18

5.7 Tota1 Performance .•••..•..••.•••.••.•.••.••.•.•.•.•••...••••.•• 18

5.8 Inventory. • • • • • • • . • • • • • • • . • • . • • • • • . • • . • • • . • • • . • • • • • • • • • • • • • • • • . 19

5.9 Further Subjects ••... •••..•••.•.• .••.••.. •••. .•• .......略... . . . . 19 References •••..•••••..•.••.•.••••••••••••••••••••.•••••••.••••.••••••••• 24

Attachments •.••••••••••.•••••••.••.•••••.••.••••••••.•••••••••..•••••••• 25

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JAERI-M 93-080

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1.緒

JAERI-M 93-080

目 次

- ・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・...................r守

n.試験計画・・ H ・H ・...・H ・....…...・H ・...・ H ・-….....・H ・-…・・H ・H ・........・ H ・-…...・H ・....…...・ H ・-…'"・ H ・.. 2

1.目 的・H ・H ・・

2. ライン構成…・H ・H ・-

2

2

3. サブシステム・ H ・H ・H ・H ・.，…...・ H ・.....・H ・H ・H ・.....・H ・..…...・ H ・.....・ H ・..…'"・ H ・..…...・H ・..… 2

4. 人員....・ H ・.....・ H ・......・H ・.......・ H ・...・ H ・.....・ H ・......・ H ・.....・H ・H ・H ・...・H ・.....・ H ・......・ H ・ 3

5. 日 程・..........・H ・.....・H ・..…….........…...・H ・"…...・ H ・..…'"・ H ・.....・H ・H ・H ・.....・ H ・......・ H ・ 3

6. 予期される危険とその対策…'"・ H ・.....・ H ・..…...・H ・.....・ H ・..…...・H ・.....・ H ・H ・H ・.....・ H ・ 3

7. 操作の概要...・ H ・......・ H ・......・ H ・.......・ H ・.....・ H ・......・ H ・H ・H ・...・ H ・..…...・H ・.....・ H ・......・ H ・ 4

8. 記 録...................................................................................................・・・・・・・・ 7

m.試験結果....・ H ・....・H ・.....・ H ・....・ H ・-…・…....・ H ・.......・ H ・.....・ H ・....・ H ・....・ H ・........・H ・....・H ・.....… 13

1. 結果の概要….....・ H ・...・ H ・.......・ H ・....・ H ・....・ H ・........・ H ・....・ H ・.....・ H ・...・ H ・....・ H ・.......・H ・... 13

2. 目的...・ H ・.....・ H ・..…...・ H ・H ・H ・..…・ H ・H ・.....・H ・..…...・ H ・.....・H ・.....・ H ・.....・ H ・.....・H ・.. 14

3. ライン構成…....・ H ・-…....・ H ・....・ H ・...・H ・.....・ H ・.....・ H ・....….....・ H ・...・ H ・-・・H ・H ・....・ H ・...... 14

4. 運転操作....・ H ・....・ H ・-・….....・ H ・....・ H ・....・ H ・....・H ・....・H ・....・ H ・...・ H ・.....・H ・....・ H ・...・H ・.. 15

4. 1 準備…....・ H ・.....・ H ・...・ H ・........................................................................ 15

4.2 トリチウム供給 H ・H ・...・H ・.，...・ H ・H ・H ・.....・H ・....・ H ・...・ H ・H ・H ・-… H ・H ・-…...・ H ・....・H ・.. 15

4. 3 不純物供給なしでの運転・…・…....・ H ・.......・H ・...・ H ・-…...・ H ・....・H ・...・ H ・.......・ H ・..… 15

4.4 不純物供給運転…・..................................................................................... 15

4. 5 トリチウム回収...・ H ・.....・H ・....・ H ・......・ H ・..…..，・ H ・..……… H ・H ・...… H ・H ・......・ H ・.... 16

4. 6 トリチウムインベントリーチェック…・ H ・H ・.......・H ・.....・ H ・.......・ H ・.......・ H ・......・ H ・..… 16

5. 結果と考案....・ H ・....・H ・....・ H ・-…...・ H ・.....・H ・.......................................................... 17

5. 1 パラジウム拡散器・...・ H ・.....・ H ・....・ H ・-…・ H ・H ・.........・ H ・........・ H ・........・ H ・.........・ H ・... 17

5.2 酸化反応器・ H ・H ・....・ H ・..…....・ H ・........・ H ・...・ H ・-….....・ H ・....・ H ・・・ H ・H ・....・ H ・.....・ H ・... 17

5. 3 コ-)レドトラップ・H ・H ・H ・H ・.....・ H ・....…… H ・H ・...・H ・H ・H ・.....・ H ・.....・ H ・......・ H ・..…… 17

5. 4 セラミック電解セル H ・H ・.....・ H ・..，・ H ・...…… H ・H ・...・ H ・.....・ H ・.....・ H ・..…… H ・H ・...… 18

5.5 ガスクロマトグラフ H ・H ・...・ H ・.....・ H ・.......・ H ・...・ H ・....・ H ・.....・ H ・'"・ H ・...・ H ・..，・ H ・-… 18

5. 6 ジJレコニウムコノ守Jレトベッド……...・ H ・.....・ H ・H ・H ・.....・ H ・.......・ H ・H ・H ・.....・H ・..…… 18

5.7 全体性能....・ H ・...・ H ・....・H ・'"・ H ・-・…・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・・ 18

5. 8 トリチウムインベントリー H ・H ・-

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JAERI-M 93-080

I.INTRODUCTION

In June 1987, the Japan Atomic Energy Research Institute (JAERI) and the United State Department of Energy ( DOE) signed a collaborative agreement ( originally 5 years ), Annex IV to the Japan/U.S. Agreement on Fusion Energy, regarding development of technology for fusion-fuel processing. Under this agreement, JAERI and DOE have continued joint operations and experiments on fusion-fuel processing technology with the Tritium Systems Test Assembry (TSTA ) at the Los Alamos National Laboratory ( LANL) [1-2].

JAERI designed and fabricated the JAERI Fuel Cleanup System (J-FCU) as a subsystem of simulated fusion fuel loop at the TSTA under this international collaboration, and installed J-FCU at the TSTA on March, 1990 [3-5]. The main function of the J-FCU is to purify and to recover hydrogen isotopes from simulated plasma exhaust while exhausting tritium free impurities. J-FCU was tested with deuterium for a year after installation [6]. Though the J-FCU was in tritium test from March, 1991, the first entire J-FCU stand-alone tritium test was carried out on June, 1991 with one gram of tritium [7].

This report describes the detail results of this test and discuss also the residual tritium inventory of J-FCU after the run.

— 1 —

JAERI-M 93-080

1. 1 NTRODUCT 1 ON

In June 1987. the Japan Atomic Energy Research Institute (JAERI ) and the United

State Departmenl of Energy ( DOE ) signed a collaborative agreemenl ( originally 5 years ).

Annex IV 10 the Japan/U.S. Agreement on Fusion Energy， regarding development of

technology for fusion-fuel processing. Under this agreement， JAERI and DOE have continued

joint operations and experiments on fusion-fuel processing technology with the Tritium

Systems Test Assembry (TSTA) at the Los Alamos National Laboratory ( LANL) [1-2].

JAERI designed and fabricated the JAERI Fue1 Cleanup System (J-FCU)ぉ a

subsystem of simulated fusion fuel100p at the TSTA under this intemational coIlaboration， and

installed J-FCU at lhe TSTA on March. 1990 [3-5]. The main funClion ofthe J-FCU is to

purify and to recover hydrogen isotopes from simulated plasma exhaust while exhausting

tritium free impurities. J-FCU was tested with deuterium for a year after instaJlation [6].

Though the J-FCU was in tritium test from March， 1991， the first entire J・FCUstand-aJone

tritium test was carried out on June， 1991 with one gram of tritium [7].

This report describes the detail results of this test and discuss also the residuaJ tritium

inventory of J-FCU after the run.

JAERI-M 93-080

II. PLAN FOR THE JAERI FUEL CLEANUP SYSTEM STAND ALONE TRITIUM TEST

1. PURPOSE This test plan outlines the first tritium testing of the JFCU (JAERI Fuel Cleanup)

System. Since the completion of the installation of the JFCU in Mar. 1990, a number of cold tests have been performed. Through these tests, many minor problems were uncovered and corrected. Function and characteristics of the major components were measured. The experience, knowledge, and skill of the personnel to operate the JFCU are considered to be sufficient to run the process with tritium. The purpose of this test is to evaluate with a DT mixture the total integrity and function of the system that purifies and recovers hydrogen isotopes from mixtures while exhausting impuriths to TWT. Complete inventory before and after this run will provide information on the effect of processing DT-impurity mixture with the JFCU on loop inventory. A small amount of tritium (~1 gram) will be used.

2. C O N F I G U R A T I O N

The test will be conducted as a stand alone run of the JFCU. All the process piping will be connected between the JFCU and TSTA main loop and safety systems. Tritium will be provided from a PC and be transferred to the JFCU after the exact quantity is measured. Process and vacuum waste streams will be processed by PEV and TWT. Secondary containments of the JFCU and the adjacent Normetex pump are monitored for tritium and controlled by the MDAC.

3. SUBSYSTEM REQUIRED The MDAC will archive data from the JFCU. It is possible to monitor all the physical

variables and to send a shutdown command from the MDAC. Oxygen concentration at the input to the JCR1 is also controlled through MDAC. TPU and LIO are used to transfer tritium to the JFCU. The amount of tritium and deuterium used for the tests will be measured using UTB inventory system. PEV and TWT will process exhaust from JFCU, both from the process and GCs. High and low pressure nitrogen, chilled water, helium, liquid nitrogen, and regular and UPS electric power are needed. Major tritium operations in other TSTA subsystems during this testing will not occur

— 2 —

JAERl-M 93-080

n. PLAN FOR THE JAERI FUEL CLEANUP

SYSTEM STAND ALONE TRITIUM TEST

1. PURPOSE

This test plan outlines the first tritium testing of the JFCU (JAERI Fuel Cle却 up)

System. Since the completion of the installation of the JFCU in Mar. 1990， a number of coJd

tests have been performed. Th即時hthese tests， many minor problems were uncovered and

corrected. Function and characteristics of the major components were measured. The

experience， knowledge， and skill of the personnel to operate the JFCU are considered to be

sufficient to run the process with tritium. The pu叩oseof this test is to evaluate with a DT

mixture the tota1 integrity and function of the system that purifies and recovers hydrogen

isotopes from mixtures while exhausting impuriti弓sto TWT. Complete inventory before and

after this run will provide infonnation on the effec~ of processing DT -impurity mixture with the

JFCU on 100p inventory. A small amount of tritium (-1 gram) will be used.

2. C 0 N F 1 G U R A T I 0 N

The test wil1 be conducted as a stand alone run of the JFCU. AlI the process piping

will be connected between the JFCU and TST A main loop and safety systems. Tritium will be

provided from a PC and be transferred to the JFCU a白erthe exact quantity is measured.

Process and vacuum waste streams will be processed by PEV and TWT. Secondary

containments of the JFCU and the adjacent Nonnetex pump are monitored for tritium and

controlJed by the MDAC.

3. S U B S Y S T E M R E Q U I R E D

The MDAC will archive data from the JFCU. It is possible to monitor all the physical

variables and 10 send a shutdown command from the MDAC. Oxygen concentration at the

inpul to the JCR 1 is also controlled through MDAC. TPU and LIO are used to transfer tritium

to the JFCU. The amount of tritium and deuterium used for the tests will be measured using

UTB inventory system. PEV and TWT will process exhaust from JFCU， b01h from the

process and GCs. High and low pressure nitrogen. chilled water， helium. Iiquid nitrogen‘and

regular and IJPS electric power are needed. Major tritium operations in other TSTA

subsystems during this testing wi1l not occur

-2一

JAERI-M 93-080

4. P E R S O N N E L

S. Konishi and J. W. Barnes will coordinate the test. All the JAERI members and a number of TSTA staff and operators are involved in the testing. TSTA operators, those who will be qualified by this run, will conduct the operation. Personnel assignments will be announced. Daily meetings will be held, and huddles called as necessary.

5. T I M E

The test will require approximately nine working days including tritium transfer and complete inventory after the run. The operation of JFCU apparatus will be conducted in the week starting on March 25. Tritium leak checking will be done in the first one or two days. If the leak check is completed in the first day, JFCU run will begin on the next day. A day or two of round-the-clock operation will be conducted. Regular working hours will apply for the other days, however, some overtime is anticipated. Two shfts or late duty may be assigned. Meeting will he held every morning. Huddles will be called when needed. Operating personnel will be on duty when major amount of tritium is being processed or contained in the process in gas phase. Personnel will be needed only during regular work hours during this period except for the assigned shift. Some overtime work may be needed depending on the progress of the test. A tentative schedule is shown in tabie 1.

6. P O S S I B L E H A Z A R D S

Approximately 4 liters (I gram) of tritium will be used in the test. Tritium leak checking should be conducted as the first part of the test. Situations that may lead to large losses of tritium to TWT initiate interlocked shutdown. In most of the emergency conditions, tritium can be recovered by the ZCB1.

Other potential hazards are related to, high and low temperature at the components, high pressure gas, possible combustible mixtures, loss of cooling water, and electric power. All the major hazards are monitored and alarmed and/or interlocked.

— 3 —

JAE.悶-M93-価。

4. P E R S 0 N N E L

S. Konishi and J. W. Barnes will coordinate the test. AII the JAERI members and a

number of TST A staff and operato時 areinvolved in the tesling. TST A operalors， those who

will be qualified by Ihis run. wiJJ conduct the operation. Personnel assignmenls will be

announced. Daily meetings will be held. and huddles calIed出 necessary.

5. T I ME

The test wiI1印刷ireapproximalely nine working days including tritium transfer and

complele invenlory after Ihe run. The operalion of JFCU apparatus wil¥ be conducted in the

week slarling on March 25. Tritium leak checking will be done in the白隠tone ortwo由Iys.If

the leak check is completed in the first day， JFCU run will begin on the next day. A day or

two of round-the-clock operation wi¥l be conducted. Regular working hours will app}y for the

other days， however司 someovertime is anticipated. Two shfts or Jate dUly may be assigned.

Meeting will he held every morning. HuddJes will be called when needed. Operating

personnel will be on duty when mりoramount of tritium is being processed or contained in the

process in gas phase. Personnel wil¥ be needed only during reguJar work hours during this

period except for the assigned shift. Some overtime work may be needed depending on the

progress of the lest. A tentative schedule is shown in tabie l.

~ POSSIBLE HAZARDS

Approximately 4 liters (1 gram) of tritium will be used in the test. Tritium leak

checking should be conducted as the first part of the test. Situations that may lead 10 large

losses of tritium 10 TWT initiate interlocked shutdown. ln most of the emergency conditions，

tritium can be recovered by the ZCB l.

Other potential hazards are relaled 10. high and low temperature at the components， high

pressu陀 gas，possible combustible mixtures， loss of cooling water， and electric power. AIl the

major hazards are monitored and alarmed and/or interlocked.

-3ー

JAERI-M 93-080

7. O U T L I N E

On the first day of the test, a 50 liter PC containing 12% of T will be mounted to the Load-in manifold in the LIO#' . Small amounts of tritium(~10 Ci) are sequentially introduced through the process piping to the JFCU and the JFCU process. Flow path from the LIO to the JFCU for tritium leak check is shown in the Fig.l. Minor leaks and other problems will be fixed if they are detected. If a major problem is uncovered, test will not proceed to the next step until it is solved.

JFCU will be operated as an isolated (non-loop) process with DT-He mixture. Tritium gas in the standard volume or PC will be transferred to the JFCU. Separation of DT from He, conversion at the catalytic reactor, trapping and decomposition of water, and gas analysis by the GC system functions will be tested to verify the system integrity. System throughput, hydrogen concentration in the bleed, conversion efficiency at the catalytic reactor, trapping efficiency at the cold traps, and capacity of the electrolysis cell will be measured with instruments such as flowmeters, hygrometers, oxygen monitors and GCs. Deuterium will be supplied from an external source to stabilize the system pressure. If the system works well, addition of minimal methane impurity will be tested. Excess hydrogen isotopes will be recovered with the ZCB1. Configuration is shown in the Fig.2.

At the end of the test, almost all of the hydrogen isotopes will be recovered at the ZCB 1. Residual gas in the process that is virtually tritium free is pumped by PEV. Amount of tritium transferred to the LPR in the TWT will be measured. Complete inventory will be done when the UTB inventory is unlocked. Standard UTB inventory procedure will be followed.

7.1 Preparation All the process connections to TSTA systems will be completed. The JFCU will be isolated from the existing TSTA systems with valves.

MMI for the above connections will be completed and tested if needed. Loop drawing will be revised.

Secondary containment will be closed and He leak checked. Tritium monitor and purge control will be installed and tested.

7.2 Unloading tritium from UTB(day 1,2) The JFCU process and connections to TSTA systems will be evacuated. Vacuum jackets for PD and JCR1 will be evacuated and isolated.

Pressure and flow transducers are calibrated to zero. A PC with known amount of tritium will be attached to LIO. Approximately 50 liter of DT will be sent to JFCU later.

# 1 UTB inventory is not unlocked yet and no transfer of tritium to and from JFCU is approved.

— 4 —

JAERI-M 93-0卸

7. OUTL 1 NE

On the first day of the test. a 50 liter PC containing ] 2% of T will be mounted to the

Load-in manifold in the LIO#) . Small amounts of tritiumトIOCi) are sequentialIy introduced

through the process piping to the JFCU and the JFCU process. Aow path from the LlO to山e

JFCU for tritium leak check is shown in the Fig.]. Minor leaks and other problems wiJI be

fixed if they are detected. If a major problem is uncovered. test will not proceed to the next

step until it is solved.

JFCU will be operated錨 anisolated (non-I∞'p) process with DT-He mixture. Tritium

gas in the standard volume or PC will be transferred to the JFCU. Separation of DT from He.

conversion at the catalytic reactor， trapping初lddecomposition of water， and gas analysis by

the GC system functions will be testedωverify the system integrity. System throughput.

hydrogen concentration in the bleed、conversionefficiency at the catalytic reactor， tlョpping

efficiency at the cold traps.創ldcapacity of the electrolysis cell will be measured with

instruments such as tlowmeters， hygrometers， oxygen monitors and GCs. Deuterium will be

supplied from an extemal source to stabilize the system pressure. If the system works well，

addition of minimal methane impurity will be testea. Excess hydrogen isotopes wiII be

recovered with the ZCB 1. Configuration is shown in the Fig.2.

At the end of the test， a1most al1 of the hydrogen isotopes will be recovered at the

ZCB 1. Residual gas i n the process that is virtually tritium free is pumped by PEV. Amount of

tritium transferred to the LPR in the TWT will be measu陀 d.Complete inventory will be done

when the UTB inventory is unlocked. Standard UTB inventory procedure will be followed.

7.1 Preparation

AlI the process connections to TST A systems will be completed. The JFCU will be isolated

from the existing TST A systems with valves.

MMI for the above connections will be completed~d tested if needed. Loop drawing will

be revised.

Secondary containment wi1l be c10sed and He leak checked.

Tritium monitor and purge control will be installed and tested.

7.2 Unloading tritium from UTB(day 1，2) The JFCU process and connections to TST A systems will be evacuated. Vacuum jackets for

PD and JCR I will be evacuated and iso1ated.

Pressure and tlow transducers are calibrated 10 zero.

A PC with known amount of tritium will be attached to LIO. Approximately 50 Hter of DT

will be sent to JFCU later.

#1 UT8 inventory is not unlocked yet and no transfer of tritium to and from JFCU is approved.

-4-

JAERI-M 93-080

Quantity of tritium is measured according to the standard inventory procedure. Rest of the tritium is recovered to the cooled U bed.

7.3 Preparation for the JFCU operation(day 2) Prepare utilities, i.e., nitrogen, liquid nitrogen. He, O2 and D2. and vacuum. Leave the Scroll pump oil circulation running.

Gas Chromatographs will be turned on and the carrier gas will be supplied. He carrier is used for GC1. GC will be calibrated with standard gas.

Glovebox will be purged with nitrogen until oxygen level goes down.

7.4 Start-up/Heating/Cooling (day 2) Make sure that the JFCU computer has sufficient memory space*2 . If not, store the log

files in a tape and delete unnecessary files. Check vacuum in RT1-PD-SCROL-RT2. Isolate RTl-PD(both sides), SCROL and RT2 by

closing AV415 and 414. Fill JCR1-CT-CEC- with helium to ca.400 torn Flow cooling water to CEC. Start heating of the CEC, JCR1 and PD.

7.5 Tritium leak check (day 3,4) Activate the glovebox monitor. Introduce small amount of tritium. Pressurize process with helium. Permeated side of the PD-SCROL-RT will be pressurized with D2. Watch for the increase of tritium level in the glovebox. When leak is suspected, sniff with a portable monitor. Penetrations for leak check are installed on the top of the box.

When the leak test is completed. Isolate RTl-PD(both sides), SCROL and RT2 by closing AV415 and 414 and pump out RT1-PD-SCROL-RT2. with PEV. Amount of tritium accepted in the LPR will be measured and recorded.

7.6 Prepare for normal operation(day 4,or 5) Isolate PD (permeated side)-Scrol-pump-RT2 under vacuum. Fill RT1-PD (feed side)-JCRl-CT-CEC loop with helium.

# 2 Memory space can be checked by the @DEV_ST_LOOP macro on the GPX or 3100. Start operation with at least 20% of memory. (Data files must be stored to tape at the end of the first week.

— 5 —

JAE阻 -M93-0剖

Quanlily of lritium is measured according to the standard inventory procedure. Rest of the

tritium is recovered 10 the cooled U bed.

7.3 Preparation for the JFCU operation(day 2)

Prepare utilities. i.e.. nitrogen. liquid nitrogen. He. 02 and 02. and vacuum. Leave lhe

Scroll pump oil circuJation running.

Gas Chromatographs will be turned on and the ca!TIer gas will be supplied. He carrier is

used for GC 1. GC will be caJibrated with SI加 dardgas.

Glovebox will be purged wirh nitrogen unriJ oxygen level g，ぽsdown.

7.4 Start-up/Heating/CooJing (day 2)

Make sure that the JFCU computer has sufficienl memory space#2 . Jf not. store the Iog

files in a tape and delete unnecess創'Yfiles.

Check vacuum in RTI・PO-SCROL・RT2.Isolale RTJ・PO(bothsides)、SCROLand RT2 by

c10sing A V415 and 414.

Fill JCRI-CT-CEC-with helium 10 ca.400 10町.

Flow cooling water to CEC.

Start heating of the CEC， JCR 1 and PO.

7.5 Tritium leak check (day 3，4) Activate the glovebox monitor.

Introduce small amount of tritium.

Pressurize process wilh helium.

Permeated side of the PD-SCROL-RT will be pressurized with 02・

Watch for the increase oftritium level in the glovebox.

When leak is suspected. sniff wilh a portable monilor. Penelrations for Jeak check are

installed on the top of the box.

When the leak test is compJeted. Isolate RTJ・PD(bolhsides). SCROL and RT2 by closing

AV41S and 414 and pump out RTI.PO-SCROL-RT2. with PEV. Amount oftritium

accepted in the LPR will be measured and recorded.

7.6 Prepare for normal operation(day 4，or 5) Isolate PO (permeated side)-ScroJ-pump-RT2 under vacuum.

Fill RTI-PD (feed side)-JCRI-CT-CEC loop with helium.

#2 Memory space can be checked by the@DEV_ST_LOOP macro on the GPX or 3100. Start operation with at least 20% of memory. (Data f;les must be stored to fape at the end ot the first week.

-5-

JAERI-M 93-080

7.7 Continuous Unit Normal Operation Start Freon Refrigerator and cold trap cycles. Set operation mode and alarm settings.*3

Establish Heating mode. Establish Stand-by mode. Start pumps. Supply T2 to the RT1-PD-SCROL-RT2 loop from UTB. Start Unit operation mode. Supply impurities. Start GC analysis. When the pressure in the RT2 becomes greater than PRA-RTl, start "UNIT" operation.

(Fig.2) Operate the system stably for several cycles.

7.8 Pause ( day 5, 6 evening, when needed) Stop impurities, and oxygen supply. Close all the boundary valves*4 . Stop scroll pump and isolate PDl-RTl-Scroll pump loop. Stop cold trap cycle and potentiostat. Scroll pump oil circulation will be left ON and isolated manually.

7.9 Restart Reset the "PAUSE" switch if it is ON. Start cold trap cycle, oxygen supply and potentiostat. Restart normal operation mode. Supply impurities. Start GC analysis.

7.10 Shut Down/tritium Recovery (day 6,7) Stop impurities. Isolate PD(Permeated side)-SCROL-RT2. by closing AV406. Recover pure hydrogen isotope to UTB. Continue to operate cold traps and the electrolysis cell. Stop oxygen supply 30 min after methane addition is stopped.. When leaving on day 6, Stop Potentiostat and the circulation pump(MBP). Restart Circulation pump and potentiostat on the following day. Heat all the cold traps and MSBs when they are almost dried out (HLR-CECIN-273KDP). Continue to electrolyze moisture in the system.

# 3 Modes settings are; DILUTION-INTERNAL, REGENERATION-EXTERNAL, PDBLEED-PRESSUBE, and UNIT loop mode. Alarm and set points settings are listed in the DTP.

# 4 Supply of He, CH 4 ,02, AV401 - 411, outlet to TWTAV412, (413), internal subioops, AV414 and 415, D2 recovery to ZCB1 AV416.

— 6 -

JAERI-M 93-080

7.7 Continuous Vnit Nor.mal Operation

Start Freon Refrigerator and cold trap cycles.

Set operation mode and alarm settingss3

Establish Heating mode.

EstabJish St叩 d-bymode.

Slart pumps. Supply T2 to the RTI-PD-SCROL-RT2 loop from UTB.

Start Unit operalion mode. Supply impurities. Start GC anaJysis.

When the pressure in the RT2 becomes greater than PRA-RTI， slart "UNIT" operation.

(Fig.2)

Operate the system stably for several cycles.

7.8 Pause ( day 5， 6 evening， when needed) Stop impurities， and oxygen supply. Close aJl the boundary valves#4 .

Stop scroIl pump and isolate PDJ-RTJ-ScrolJ pump]∞'p.

Stop cold trap cyde and potentiostat.

Scroll pump oil circulation will be left ON and isolatf"d manually.

7.9 Restart

Reset the "PAUSE" switch jf it is ON.

Start cold trap cycle， oxygen supply and potentiostat.

Restart normal operation mode.

Supply impurities. Start GC加 alysis.

7.10 Shut Down/tritium Recovery (day 6，7) Stop impurities. Isolate PD(Penneated side)-SCROL-RT2. by c10sing A V406.

Recover pure hydrogen isotope 10 UTB.

Continue to operate cold traps and the electrolysis ceII.

Stop oxygen supply 30 min a白ermethane addition is stopped..

When leaving 0[/ day 6， Stop Potentiostat卸 dthe circulation pump(MBP).

){estart Circulation pump and potentiostat on the following day.

Heat all the cold traps and MSBs when they are almost dried out (HLR-CECIN向 273KDP).

Continue to electrolyze moisture in the system.

#3 Modes settings are; DILUTION-INTERNAL， REGENERATION-EXTERNAL， PDBLEED-PRESSURE， and UNIT loop mode. Alarm and set points settings are listed in the OTP.

#4 Supply of He， CH4， 02， AV401・411，outlel to TWTAV412， (413)， internal subloops， AV414 and 415，02 recovery 10 ZCB1 AV416.

-6-

JAERI-M 93-080

Turn off the potentiostat. Turn off pumps. Cool-down the system. Pump out the process with PEV. Amount of tritium accepted in the LPR will be measured and recorded.

7.11 ZCBl regeneration and inventory (day 8,9) The ZCBl that was used for the tritium recovery from JFCU will be heated up and

inventoried. Follow standard inventory procedure.

8. DATA Data will be recorded in the JFCU computer. Monitoring at MDAC and archiving will

also be done. A lab notebook for the JFCU will be used for the formal logging of the operations. Major configurations and "trends" will be printed out. Tritium inventory information will be given to the custodian.

Table 1 SCHEDULE

day date Subject 1 Attach PC to LIO, Process Connection, JFCU evacuation 2 Utility preparation, GB purging. Component heating/cooling. 3 Triti um leak check of JFCU 4 Tritium leak check of JFCU, Component heating 5 Steady Operation-Pause-Shift 6 Sh>«t down, tritium recovery-Pause 7 Triuum recovery, CEC cooling. 8 ZCBl regeneration 9 Inventory

- / ;

JAERI-M 93-0剖

Tum off the potentiostat.

Tum off pumps. CooJ-down the system.

Pump out the process with PEV. Amount of tritium accepted in the LPR will be measured

and recorded.

7.11 ZCBl regeneration and inventory (day 8，9) The ZCB I lhal was used for lhe lritium recovery from JFCU will be heated up叩 d

inventoried. Follow sl加 dardinventory procedure.

8. DATA

Data will be recorded in the JFCU computer. Moniioring at MDAC加 darchiving will

also be done. A lab notebook for the JFCU、'/iIIbe used for the formal lugging of the

operations. Major configurations and "lrends" will be printed out. Tritius1 ιventory

in[onnation wiU be given to the custodian.

day date

2

3

4

5

6

7

8

9

Tatle 1 SCHEDULE

Subject

Attach PC to LIO，針。cessConnection， JFCU evacuation

Utility preparation， GB purging， Component heating!cooling.

Tritium leak check of JFCU

Tritium leak check of JFCU， Component heating

Steady Operation-Pause-Shift

Sl川 tdown， tritium recovery-Pause

'i'ritlum recovery， CEC cooling.

ZCB I regeneration

Inventory

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JAERI-M 93-080

III. RESULTS FOR THE J—FCU STAND ALONE TRITIUM TEST

1. SUMMARY The first tritium testing of the JAERI Fuel Cleanup system (JFCU) was successfully

performed with I g tritium. All components were operated safely and worked well during all operations. Non-impurity fuel processing operation was performed for 8-9 hours almost continuously and fuel processing operation with a few % of methane was performed for 4-5 hours safely. During these fuel processing operations, the "External" Cold Trap (CT) regeneration line and "Internal" Catalytic Reactor (JCR1) dilution line were selected. The stream to the Tritium Waste Treatment (TWT) system was almost constant at about 5.3 Nl/min ( almost all He gas ) and its tritium level was lower than 50 Ci/m3.

When 1 g of tritium was supplied to JFCU, a very small tritium leak was measured and found on a piping weld on the Booster Pump (BP). No other leak was found. Secondary containment system worked well and kept the Glove Box (GB) tritium level less than 4 mCi/m3, so that tritium run could be continued safely. However, repairing of the above small leak should be done before next 10 g tritium run.

When each CT was changed periodically ( once per an hour), a small humidity spike at the outlet of CTs was detected because of incomplete regeneration of small molecular sieve beds (JMSB3 ~ 5) at the outlet of CTs. In future tests, complete regeneration of these molecular sieve beds should be done. In spite of the above situation, no significant ritium exhausting to TWT was detected and the system was always safe, because the interlock system of JFCU worked well.

All tritium was recovered in the Zirconium Cobalt Bed (ZCB1) of JFCU and no tritium was detected exhausting to the TWT from the JFCU process evacuation at the shut down operation. After the shut down, ZCB1 was regenerated and its inventory was checked. Almost hydrogen isotopes were recovered from ZCB1 to PCs. The volume recovered was almost equal to the imput volume, but recovered tritium was only 0.67 gram (-70% of initial supply). After enough ZCB I regeneration, residual tritium inventory was investigated by calorymetory and hydrogen exchange method. Finally, 0.91 grams of tritium was identified.

Through these operations, operators and staff acquored operating experience and the total integrity and function of JFCU and related TSTA systems have been proven with tritium.

— 13 —

JAER1-M 93-080

皿.RESULTS FOR THE J-FCU STAND ALONE TRITIUM TEST

1. SUMMARY

The first tritium testing ofthe JAERI Fucl Cleanup system (JFCU) was successfully

performed with 1 g tritium. AII components were operated safely and worked well during al1

operations. Ncn-impurity fuel processing operation was performed for 8-9 hours almost

continuously and fuel processing operation with a few % of methane was performed for 4・5

hours safely. During these fuel processing operations， the "Extemal" Cold Trap (CT)

regeneration line and "Intemal" CataIytic Reactor (JCR 1) dilution line were selected. The

stream to the Tritium Waste Treatment (TWT) system was aImost constant at about 5.3 NI/min

( almost all He gas ) and its tritium level was lower th加 50Ci/m3.

When 1 g of tritium w部 suppliedto JFCU， a very smaIl tritium leak was measured加 d

found on a piping weld on the Booster Pump (BP). No other leak was found. Secondary

containment system worked well and kept the Glove Box (GB) tritium levelless th佃 4

mCi/m3， so that tritium run could be continued safdy. However， repairing of the above smaIJ

leak should be done before next IO g tritium run.

When each CT was changed戸巾dically( once per an hour )， a small humidity spike at

the outlet of CTs was detected because of incomplete regeneration of small molecular sieve

beds (JMSB3 -5) at the outlet of CTs. In future tests， complete regeneration of these

molecular sieve beds should be done. In spite of the above situation， no significant ritium

exhausting to TWT was detected and the system w出 alwayssafe， because the interlock system

of JFCU worked well.

All tritium was recovered in the Zirconium Cobalt Bed (ZCB 1) of JFCU and no tritium

was detecled exhausling to the TWT from the JFCU process evacuation at the shut down

operation. After the shut down， ZCB I was regenerate(l. and its inventory was checked.

Almost hydrogen isotopes were recovered from ZCB] to PCs. The volume recovered was

almost equal 10 the imput volume， but陀 coveredtritium was only 0.67 gram (-70% of initial

supply). After enough ZCB 1 regeneration， residuaI tritium inventory was investigated by

calorymetory and hydrogen exchange method. Finally， 0.91 grams oftritium was identified.

Through these operations， operators and staff acquored operating experience and the totaI

integrity and function of JFCU and related TST A systems have been proven with tritium.

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JAERI-M 93-080

2. PURPOSE

This test is the first tritium test of JFCU system. The main part of this test was performed during June 27 - 28. 1991.

The purpose of this run is to evaluate with a DT mixture the total integrity and function of the system that purifies and recovers hydrogen isotopes from mixtures while exhausting impurities as tritium free species to TWT. Complete inventory before and after this run will provide information on the effect of processing DT-impurity mixture with the JFCU on loop inventory.

3. C O N F I G U R A T I O N

The test was conducted as a stand alone run of the JFCU. Figure 2 in the test plan ( previous section ) illustrates the major flows of JFCU under this test. Other systems were used in support of the test. These systems were Load in/out (LIO) and Transfer pumping unit (TP1) for tritium supply and inventory; the TWT system for JFCU exhaust processing; Process evacuation (PEV) system for system evacuation and GC sampling; and various utility, safety, and monitoring systems.

Table 3-1 shows components and system control situation. Table 3-2 shows alarm setting situation.

— 14 —

JAERI-M 93-080

2. PUR POS E

This lesl is the tirst tritium lest of JFCU system. The main part of this lesl was

pcrformed during Junc 27・28.1991.

The purpose of Ihis run is 10 evaluale wilh a DT mixture the lotaJ integrity and function of

the system Ihat purifies and recovers hydrogen isotopes from mixtures while exhausting

impurities as Iritium free species 10 TWT. Complete inventory before and after this run wil¥

provide infonnation on the effect of processing DT-impurity mixture with the JFCU on loop

II1venlory.

3. C 0 N F I G LJ R A T I 0 N

The test was conducted as a sland alone run of the JFCU. Figure 2 in the test pJan (

previous section ) iIIustrates the major tlows of JFCU under this test. Other systems were

used in support of the test. These systems were Load inJout (LlO) and Transfer pumping unit

(TP I ) for tri li um suppl y and inventory; the TWT system for JFCU exhaust processing;

Process evacuation (PEV) system for system evacuation and GC sampling; and various utiIity，

safety. and monitoring syslems.

Table 3・1shows components and system controI situation.

Table 3・2shows alalT'1 setting situation.

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JAERI-M 93-080

4. OPERATIONS 4.1 Preparations

All GBs used in this test (LIO, TP1, and JFCU) were leak-checked again and found leak tight by much effort of technicians during June 22 - 27.

All components were heated and cooled to operation temperature before June 26 and leak tightness of all JFCU process line were checked again at the operation temperature with a small amount of tritium less than 20 Ci on June 27.

Zero adjustments of all flow meters and controllers were carried out on June 27. GC analysis calibration and oxygen monitor calibrations were also performed on June 26-27.

4.2 lg tritium supply Before the tritium introduction lines involved were evacuated. Tritium load-in started at 15:21 on June 27. About 35 liter of HDT mixture with 1 g

tritium were supplied from LIO-PC to JFCU-RTl through TP1. Hydrogen isotopes were purified by the Palladium diffuser (PD) and stored at JFCU-RT2. Load-in stopped at 16:06. Some amount of residual gas in the transfer piping was evacuated to TWT. Details of the amount of tritium supplied to JFCU are summarized at the section of "Inventory" (5-8) and in the Attachment 6-3.

4.3 Non-impurity operation Following the "Detailed operation procedure for JFCU" (TTA-TP-118-15, R0), valves

positions and component heating and pump conditions were checked, CT preparation was done, operating mode was selected, and control parameters were checked (" Heating Mode" was established.).

After the tritium load-in, Metal bellows pump (MBP) was turned on, Oxygen supply was started, and potentiostat was turned on ("Stand-by Mode" was established).

Helium supply was started for CT regeneration (18:30), and the system pressure and flow rate were adjusted to stabilize the system. The oxygen control program did not work well, so the flow rate of oxygen was set manually. Then hydrogen isotopes circulation was started continuously (22:00).

GC sampling analysis program was started after checking the "program timer" of GC ( 24:00). Sampling points were #3,#4,#5 or #2, #3, #5 and this analysis was continued automatically during the night.

This operation was stopped at 6:30 on June 28.

4.4 Impurity operation After some preparation for impurity injection, methane (CH4) supply was started to

JFCU-RTl ( 50 ml/min )(8:00). JFCU-SAFETY program was started by MDAC and Oxygen

— 15 —

JAERI-M 93-080

4. 0 P E R A T J 0 N S

4.1 Preparations

AIl GBs used in this test (LIO. TPl， and JFCU) were leak-checked again and found leak

tight by much effort of technicians during June 22 -27.

AIl components were heated加 dcooled to operation tempemture before June 26 and leak

tightness of all JFCU process line were checked again at the operation tempemture with a small

amount of tritium less than 20 Ci on June 27.

Zero adjustments of all flow meters and controllers were carried out on June 27. GC

analysis calibration and oxygen monitor caIibrations were also performed on June 26-27.

4.2 19 tritium supply

Before the tritium introduction lines involved were evacuated.

Tritium load-in started at 15:21 on June 27. About 35 liter of HDT mixture with 1 g

tri1ium were supplied from LIO-PC 10 JFCU・RTlthrough TPI. Hydrogen isotopes were

purified by the Palladium diffuser (PD) and stored at JFCU-RT2. Load-in stopped at 16:06.

Some arnount of residual gas in the transfer piping was evacuated to TWT. Detai!s of the

amount of tritium supplied to JFCU are summarized at the section of "Inventory" (5-8) and in

the Attachment 6-3.

4.3 Non-impurity operation

Following the "Detailed operation procedure for JFCU" (TTA-TP-118-15. RO)， valves

positions and component heating and pump conditions were checked. CT preparation w拙

done， operating mode was selected， and control parameters were checked (" Heating Mode"

was estabJished.).

After the tritium load-in， Metal bellows pump (MBP) was tumed on， Oxygen supply w酪

started， and potentiostat was turned on ("Stand-by Mode" was established).

Helium supply was started for CT regeneration (18:30)， and the system pressure and

flow rate were adjusted to stabilize the system. The oxygen control program did not work

well， so the f10w rate of oxygen was set manually. Then hydrogen isotopes circulation was

started continuously (22:00).

GC sampling analysis program was started aれerchecking the "program timer" of GC (

24:00). Sampling points were #3，#4，#5 or #2， #3， #5 and this analysis was continued

automatically during the night.

This operation was stopped at 6:30 on June 28.

4.4 Impurity operation

After some preparation for impurity i吋ection，methane (CH4) supply was started to

JFCU-RTl ( 50 ml/min )(8:00). JFCU・SAFETYprogram was started by MDAC and Oxygen

- 15ー

JAERI-M 93-080

control was turned to "Auto". GC sampling points were changed to #4, #5 in order to check the methane combustion situation.

CH4 supply was stopped at 12:30 and this operation was finished.

4.5 Tritium recovery 4.5.1 main-loop ( RT-2 )

Just after finishing impurity injection, hydrogen isotopes circulation was also stopped and all hydrogen isotopes in the JFCU-RT2 were recovered by the Zirconium cobalt bed (ZCB1), operating pumps continuously.

4.5.2 recovery loop dry-up operation Helium injection was stopped, exhausting to TWT was stopped, and Oxygen supply was

also stopped (all boundary valves were closed). CT regeneration line was turned to "Internal". "TSTA-SCRAM" signal was sent to JFCU from MDAC just after the start of dry-up operation and MDAC kept JFCU in "pause". Therefore, the dry-up operation was restarted after some modification of the "JFCU-SAFETY" program. This dry up operation was continued for a total of 20 hrs, repeating operation and pause down of the system. The dry-up operation was completed on July 8. All hydrogen isotopes were recovered by ZCB1 and residual gases ( almost all Helium) were evacuated to TWT.

4.6 Inventory check ZCB 1 was regenerated twice and the released hydrogen isotopes were transferred to LIO-

PCs through TPl, following the detailed test plan (TTA-TP-118-16, RO). Before the second regeneration, about 19 Nl of H2 was supplied. The isotopic composition was measured by mass spectrometer. After enough ZCB 1 regeneration, residual tritium inventory in the small molecular sieve bed (JMSBs) and JCR1 was investigated by calorymetory and hydrogen exchange method, respectively.

— 16 —

JAE阻 -M93-080

control was turned to "Auto". GC sampling points were changed to #4， #5 in order 10 check

the methane combustion situation.

CH4 supply was stopped at 12:30 and this operation was finished.

4.5 Tritium recovery

4.5.1 main-Ioop ( RT・2)

Just after finishing impurity injection， hydrogen isotopes circulalion was a1so stopped

and al! hydrogen isotopes in the JFCU-RT2 were recovered by the Zirconium cobalt bed

(ZCB 1)， operating pumps continuously.

4.5.2 recovery loop dry-up operation

Helium injection was stopped， exhausting to TWT was stopped， and Oxygen suppJy was

also stopped (all boundary valves were c1osed). CT regeneration line was turned to "Intemal".

"TSTA-SCRAM" signal was sent to JFCU from MDAC j山 tafter the start of dry-up operation

and MDAC kept JFCU in "pause". Therefore， the dry-up operation was restarted after some

modification of the "JFCU-SAFETY" program. This dry up operation was continued for a

total of 20 hrs， repeating operation and pause down of the system. The dry-up operation was

completed on July 8. AII hydrogen isotopes were recovered by ZCB 1 and residual gases (

almost all Helium ) were evacuated to TWT.

4.6 Inventory check

ZCB 1 was regenerated twice and the released hydrogen isotopes were transferred to LIO-

PCs through TPI， following the detailed test plan (TTA句 TP-118・16，RO). Before the second

regeneration， about 19 NI of H2 was supplied. The isotopic composition was measured by

mass spectrometer. After enough ZCB 1 regeneration， residual tritium inventory in the small

molecular sieve bed (JMSBs) and JCR 1 was investigated by calorymetory and hydrogen

exchange method， respectively.

au

JAERI-M 93-080

5. R E S U L T S

5.1 Palladium diffuser During this test, the Palladium diffuser (PD) was controlled at 573 K and worked well.

The amount of purified hydrogen isotopes* was about 1150 Nl. ( 700 Nl from non-impurity operation, 450 Nl from impurity operation ). Purification ratios** were more than 87 % during non-impurity operation and more than 94 % during impurity operation. Feed flow rate*** was about 5.5 ~ 9 Nl/min and its hydrogen concentration*** was 5 ~ 40 %. Impurities (CH4 and water) did not affect much the PD function.

* : calculated by the integration of "jfcu-f-vactpu". ** : calculated from the mean values of hydrogen feed {" jfcu-f-vactpu") and of

combustion humidity ("jfcu-hum-jcrlex" and "jfcu-i-wece"). (GC data showed some poor purification performance, however, it might be caused by poor calibration of GC, comparing other system data.)

*** : calculated from the values of "jfcu-f-vactpu" and "jfcu-f-cecin".

5.2 Catalytic reactor During this test, catalytic reactor (JCR1) was controlled at 773 K. All hydrogen isotopes

and methane were completely oxidized by the JCR1 if there was enough oxygen. It was not found any tritiated species at the outlet of CT under the stabilized condition by GC and by tritium monitor of JFCU. CH4 combustion effectiveness was also measured by GC*

The oxygen control program sometimes did not work well, however, its flow rate could be control manually and effectively. * : CH4 concentration at the inlet of JCR 1 was about 0.2 % and ideal combustion CO2

cone, was about 0.7 %.

5.3 Cold traps During the stabilized condition, Cold Traps (CTs) collected almost all moisture and were

regenerated completely and periodically by using Helium gas from an outside cylinder(~5.3 Nl/min). The trapping factor was more than 10^ under stabilized condition. The total collected water volume* in each CT was about 0.4 mol/hr under non-impurity operation and was about 1.1 mol/hr under impurity operation. The controlled differential pressure was 200 torr and the feed flow rate of CT was about 17 Nl/min. (It was the same flow rate as JCR1.)

CT's water collection performance was proven completely at the last cold testing, however, small humidity spikes were found periodically matching the CT changing time. It was considered that the regeneration of the small molecular sieve beds was poor. In the future test, complete regeneration of these molecular sieve beds should be done before use.

Detail humidity fluctuation around CTs was shown in figure 3-1. * : calculated from the mean values of "jfcu-i-wece", "jfcu-hum-cecin", jfcu-hum-

cecex", and "jfcu-hum-jcrlex".

— 17 —

JAERI-M 93-080

5. R ES UL TS

5.1 Palladium diffuser

During this test. the Palladium diffuser (PD) was controlled at 573 K and worked well‘

The amounl ofpurified hydrogen isotopes* was about 1150 Nl. (7∞NI from non-impurity

operation. 450 NI from impurity operation). Purification ratios料 weremore than 87 %

during non-impurity operation and more than 94 % during impurity operation. Feed f10w

rate*** was about 5.5 -9 NI/min and its hydrogen concentration料，*was 5 -40 %.

lmpurities (CH4 and water ) did not affect much the PD function.

* **

: calculated by the integration of "jfcu-f-vactpu".

: calculated from the mean values of hydrogen fi先ee吋d(" jfc叩u-fι-v刊actp仰u"ヲ)and of

combustion humidity (ぐrり"jfcαu砕u-Iト吋-1占h】um-サj炉crlex"and"γJti化cu怯肘IトI-I寸iト-wece")

(GC data showed some poωor purification performance， however， it might be caused

by poor calibration of Gc， comparing other system data.)

*料:calculated from the values of "jfcu-f-vactpu" and "jfcu-f-cecin".

5.2 Catalytic reactor

During this test， catalytic reactor (JCR 1) was controlled at 773 K. AI1 hydrogen isotopes

and methane were completely oxidized by the JCR] ifthere was enough oxygen. It wa<; not

found any tritiated species at the outlet of CT under the stabilized condition by GC加 dby

tritium monitor of JFCU. CH4 combustion effectiveness was a]so measured by GC. *

The oxygen control progIヨmsometimes did not work well， however， its f10w rate could

be control manually and effectively.

* : CH4 concentration at the inlet of JCR 1 was about 0.2 % and ideal combustion C02

conc. was about 0.7 %.

5.3 Cold traps

During the stabilized condition， Cold Traps (CTs) collected almost all moisture and were

regenerated completely and periodically by using Helium gas from an outside cylinderト5.3

NI/min). The trapping factor was more than 104 under stabilized condition. The tota] collected

water volume* in each CT was about 0.4 mol/hr under non-impurity operation and was about

1.] mol/hr under impu巾yo戸ration.The controlled differential pressu陀 Wぉ 2∞to汀 andthe

feed f10w rate of CT was about 17 NI/min. ( It was the same f10w rate as JCR 1. )

CT's water collection performance was proven completely at the last cold testing，

however， small humidity spikes were found periodicaJly matching the CT changing time. It

was considered that the regeneration of the small molecular sieve beds was poor. In the future

test， complete regeneration of these molecular sieve beds should be done before use.

Detail humidity f1uctuation around CTs was shown in fi忌日付 3-1.

* : calculated合omthe mean values of "jfcu-i-wece"， "jfcu-hum-cecin"， jfcu-hum-

cecex"， and "jfcu-hum-jcrlex".

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JAERI-M 93-080

5.4 Ceramic electrolysis cell The Ceramic Electrolysis Cell (CEC) was controlled at 1023 K. Its potential between the

inside and outside of the cell tubes was controlled to be 0,9 - 1.1 Volt by the reference electrode of the potentiostat ("jfcu-v-rece"). The differential pressure between the inside and the outside of the cell tubes was roughly controlled within - 200 ~ - 500 torr manually.

In the non-impurity operation, almost all moisture from regenerated CTs (about 0.4 mol/hr* ) was decomposed completely by CEC. In the impurity operation, a large part of that moisture ( about 0.6 mol/hr (-55%)*) was decomposed effectively.

During this test, CEC function was better because the line for CT regeneration was selected to "external". This means that CEC was not affected by excess oxygen from JCR1. In the future lest, CEC function will be better, because CEC can be heated up to 1073 K and its potential can be set to 1.3 Volt.

Detail CEC current of water decomposition was shown in figure 3-2. * : calculated from the mean value of "jfcu-i-wece".

5.5 Gaschromatographs The sampling program and analysis program worked automatically. Several samples at

the sampling points #2, #3, #4, #5 were taken periodically. Sometimes the hydrogen isotopes peak was missed during annalysis, however, this peak was recalculated manually after the run. All results of GCs are shown in APPENDIX 6.2.

During this test, all sampling pressures were too low compared to the standard for calibration. To take more reliable data, the sampling program and/or calibration technique should be adjusted for each sample point pressure situation.

5.6 Zirconium cobalt bed During the dry-up operation and inventory check operation, the zirconium cobalt bed

(ZCB1) worked well. All hydrogen isotopes were recovered safely and quickly. Almost all hydrogen isotopes stored was released by regeneration of ZCB 1 using JFCU Scroll pump.

5.7 Total performance As described above, all components were operated safely and worked well during all

operations. Non-impurity fuel processing was performed for 8-9 hours almost continuously and fuel processing operation with a few % of methane was performed for 4-5 hours safely. During these fuel processing operations, the "External" Cold Trap (CT) regeneration line and "Internal" Catalytic Reactor (JCR1) dilution line were selected. Detail trends of system flow rates and pressures were summarized in figure 3-3 and 3-4.

The stream to the Tritium Waste Treatment (TWT) system was almost constant at about 5.3 Nl/min ( almost all Helium gas ) and its tritium level was lower than 50 Ci/m3.

When each CT was changed periodically ( once per hour), a small humidity spike at the outlet of CTs was detected because of incomplete regeneration of small molecular sieve beds.

— 18 —

JAERI-M 93-080

5.4 Ceramic electrolvsis cell

The Ceramic Electrolysis Cell (CEC) was controlled at 1023 K. Its potential between the

inside and outside ofthe cell tubes was controlled to be 0.9・1.1Volt by the reference

electrode of the pOlemioslat ("jfcu-v-rece"). The djfferential p問 ssu陀 betweenthe inside and

the outside ofthe cell tubes was roughly controlled within ・2∞~・5∞torrmanually.

In the non-impurity operation. almost all moisture from regenerated CTs (about 0.4

mol/hr* ) was decomposed completely by CEC. In the impurity operation， a large part ofthat

moisture ( about 0.6 mol/hrト55%)*)was decomposed effectively.

During this test. CEC function was better because the line for CT regeneration was

selected to "external". This means that CEC was not affected by excess oxygen from JCR1.

In the future test， CEC function will be better. because CEC can be heated up to 1073 K and its

potential can be set to 1.3 Volt.

*

Detail CEC current of water decomposition was shown in figure 3-2.

: calculated from the mean value of "jfcu-i-wece".

5.5 Gaschromatographs

The sampling program加 danalysis program worked automatically. Several samples at

the sampling points #2. #3. #4、#5were taken periodically. Sometimes the hydrogen isotopes

peak was missed during annalysis. however. this peak was recalculated manually after the run.

AII resulls of GCs are shown in APPENDlX 6.2.

During this test， all sampling pressures were too low compared to the standard for

calibration. To take more reliable data司 thesampling program and/or calibration technique

should be adjusted for each sample point pressure situation.

5.6 Zirconium cobalt bed

During the dryぺlpoperation and inventory check operation. the zirconium cobalt bed

(ZCB 1) worked well. AII hydrogen isotopes were recovered safely and quickly. Almost al!

hydrogen isotopes stored was released by regeneration of ZCB I using JFCU Scrol1 pump.

5.7 Total performance

As described above. all components were operated safely and worked well during all

operations. Non-impurity fuel processing was performed for 8-9 hours almost continuously

and fuel processing operation with a few % of methane was performed for 4・5hours safely.

During these fuel processing operations. the "External" Cold Trap (CT) regeneration line and

"Internal" Catalytic Reactor (JCR 1) dilution line were selected. Detaillrends of system tlow

rates and pressUl・eswere summarized in figure 3-3 and 3-4.

The stream to the Tritium Waste Treatment (TWT) system was almost constant at about

5.3 NI/min ( almost all Helium gas ) and its tritium level was lower than 50 Ci/m3.

When each CT was changed periodically ( once per hour ). a small humidily spike at the

outlet of CTs was detected because of incomplete regeneration of small molecular sieve beds.

- 18ー

JAERI-M 93-080

However, no significant tritium exhausting to TWT was detected and the system was always safe, because the interlock system of JFCU worked well.

All tritium was recovered in the Zirconium Cobalt Bed (ZCB1) of JFCU. In order to decompose the residual moisture, dry-up operation was continued for 20 hrs (total).

Through this run, the total integrity and function of JFCU and related TSTA systems have been proven with tritium.

5.8 Inventory All result of inventory check were summarized in attachment 6.3. In the ZCB 1, the total recovered amount (~ 85 Nl) was about 10 Nl larger than the input

value. Almost difference was from the amount of Deuterium. We also found from the comparison between 1st and 2nd regeneration of ZCBl that the 7

~ 8 Nl of hydrogen isotopes could remain in ZCBl if its regeneration was poor. (JFCU Scroll and Booster pumps should be used for ZCB I complete regeneration.) So, the above 10 Nl additional recovered amount from ZCBl is considerable if the regeneration at the last cold run ( Deuterium ) was not completed.

On the other hand, initial supplied tritium (1.03 gram) was not recovered completely. Only 0.67 grams of tritium recovered in the ZCBl. After the residual tritium inventory check in the JFCU, about 0.! grams of tritium existed in the JMSBs and about 0.1 grams of tritium also recovered from the JCRI. During all operation, about 0.04 grams of tritium was exhausted to the TWT. Therefore, final inventory difference was

1.03 - ( 0.67 + 0.10 + 0.10 + 0.04) = 0.12 gram. From the consideration of residual hydrogen isotopes in ZCB 1 using 1st and 2nd

regenerated hydrogen isotopes composition, residual amount of hydrogen isotopes was calculated to be about 0.6 Nl and its tritium was about 0.001 gram, if residual gas composition would be equal to the recovered one.

From the consideration of the amount of exchanged tritium (- OT type ) and /or that of stayed tritium by water form, some amount of tritium would stay in the piping of the JFCU and JCR1.

5.9 Further subjects - BP leak repairing. - Mass flow meter (pdin) and controller (twtinh) replacing, and zero adjusting. - JMSB3 ~ 5 regeneration ( check the last cold test situation (at shut down)). - GC sampling program and/or re-calibration. - Check 02 concentration control by MDAC. - Check "JFCU-SAFTY" program by MDAC.

— 19 -

JAERI-M 93-080

However. no significant tritium exhausting 10 TWT w出 detectedand the system was always

safe. because thc interlock system of JFCU worked well.

AII tritium was recovered in the Zirconium Cobalt Bed (ZCB 1) of JFCU. In order to

decomposc thc rcsidual moisture. dry-up operalion was continued for 20 hrs (total).

Through this run. the total intcgrity and function of JFCU and related TSTA systems

have been proven with tritium.

5.8 Inventory

AII result of invenlory check were summarized in attachment 6.3.

In the ZCB 1. the 10lal recovered amount ト85NI) was about 10 NI larger th叩 theinput

value. Almosl difference W:lS from the amount of Deulerium.

We also found from lhe comparison between 1 st and 2nd regeneration of ZCB 1 that the 7

-8 NI of hydrogen isotopes could remain in ZCB 1 if its regeneration was poo仁(JFCU Scroll

and Booster pumps should be used for ZCB I complete regeneration. )

So， lhe above 10 NI additional recovered amount from ZCBI is considerable ifthe regeneration

at the lasl cold run ( Deuterium ) was not completed.

On the other hand， initial supplied tritium (1.03 gram) was not recovered completely.

Only 0.67 grams of trilium recovered in the ZCB 1. After the residual tritium inventory check

in the JFCU司 about0.1 grams of tritium existed in the JMSBs and about 0.1 grams of tritium

also recovered from lhe JCR 1. During all operation. about 0.04 grams of tritium was

exhausted 10 the TWT. Therefore， tinal inventory difference w部

1.03 -( 0.67 + 0.10 + O. 10 + 0.04) = 0.12 gram.

From the consideration of residual hydrogen isotopes in ZCB 1 using 1 sl and 2nd

regeneraled hydrogen isotopes composition， residual amount of hydrogen isotopes was

calculated to be about 0.6 Nl and its tritium was about 0.00 I gram， if residual gas composition

would be equal to thc recovered one.

From the consideration of the amount of ex.changed tritium ( -OT typc ) and /or that of

stayed tritium by water fonn. some amount of tritium would stay in lhe piping of the JFCU and

JCRI.

5.9 Further subjects

-BP leak repairing.

-Mass f10w meter (pdin) and controller (twtinh) replacing， and zero adjusting.

ーJMSB3-5 regeneration ( check the last cold test situation ( at shut down )).

-GC sampling program and/or re-calibration.

-Check 02 concentration control by MDAC.

-Check "JFCU-SAFTY" program by MDAC.

-19 -

JAERI-M 93-080

Table 3. 1 Components and system control situation.

Components temperature

Palladium diffuser(PD)

Catalytic reactor (JCR1)

Cold traps (CTs)

Ceramic electrolysis cell (CEC)

Zirconium cobalt bed (ZCB1)

System selection

CT regeneration

JCR1 dilution

PD bleed control

573 K

773 K

160 K (trapping) 343 K ( regenerating)

1023 K

723 K ( regenerating)

"External"

"Internal"

"Pressure"

System control parameter setting

IDENTIFICATION SETTING VALUE UNIT

PRCA-OFCUEX 600,0l TORR PRCA-I33IN 625.0 TORR PRCA-PDEX 622.0 TDRR PRCA-RT2 600.0 TORR PRCA-ZCB2EX 700.0 TORR FRC-CECIN 5.600 NL/MIN FRC-CH43UP 0.000 NL/MIN FRC-JCR1BYP 20.00 NL/MIN

FRC-JCR2IN 0.000 NL/MIN

IDENTIFICATION SETTING VALUE UNIT

FRC-NH3SUP 0.000 NL/MIN FRC-OXHESUP 0.000 NL/MIN FRC-PDEX 6.380 NL/MIN FRC-RMIN 1.000 NL/MIN TRCA-CECIN 333.0 K TRCA-JCR2EX 313.0 K VLRC-WERE 0,700 VOLT VLRA-WECE a. ooo VOLT PDRC-CT 200,0 TORR 0RCA-JCR1EX i.000 V.

20 —

Table 3.1

Comooncnls IClllDcrawrc

Palladiulll diffuscr (PD)

Calalylic rcaclor (JCR 1)

Cold lraps (CTs)

Ceramic eleclrolysis cell (CEC)

Zirconium cobalt bed (ZCB 1)

Svstem selection

CTr，巴generation

JCR 1 dilution

PD bleed control

System control parameter setting

IDENTIFIC向TION SETTING V向LUE

PRC内・JFCUEX 600 01

PRC向-I3SIN 625~Q

PRCA-PDEX 622~Q

PRC向-Rr2 600，Q

PRC内司ZC82Eχ ZOO ，~

FRC-CECIN S--.flOJ2

FRC-CH43UP 0.000

FRC・JCR1BYP 20.00

FRC・JCR2IN Q....ililQ

JAERI-M 93-080

Components and system control situation.

573 K

773K

160 K ( trapp~ng) 343 K ( regcncrating)

1023 K

723 K ( rcgencrating)

"Extemal"

"lntemaJ"

"Pressure"

urHT IDENTIFIC向T工ON SETTING V向lUE UNIT

TORR FRC-NH3SUP 0，000 NlIMIN

TORR FRC-OXHESUP 0.000 Nl/MIN

TORR FRC-PDEX 6.380 Nl/M工N

TORR FRC-RMIN 1.000 NlIMIN

TORR TRC向・CECIN 333.0 K

Nl/MIN TRC向・JCR2EX 313.0 K

Nl/M工N VlRC-WERE 0.700 VOLT

NlIM工N VlR向司WECE 円 000 VOLT

PDRC-CT 200~Q TORR

NlI阿IN ORC向-JCR1Eχ 1.......Q.Q.Q χ

-20-

JAERI-M 93-080

Table 3. 2 Alarm setting situation

Alarm parameter setting ( pressure )

IDENTIFICATION LOU) L H HH HIGH UNIT

PRA -RT1 75O.0 950,0 950,0 TORR PRCA-RT2 700.0 950.0 TORR PRCA-PDEX 850.0 TORR PRA -ZCB1EX 950.0 950,0 TORR PRCA-2CB2EX 750.0 850. 0 TORR PRA -SCROLIN 10.00 TORR PRCA-ISSIN 750.0 R5O.0 85<). O TORR PRCA-JFCUEX 750.0 RRO.O TORR PRA -TMPEX 25.00 P5 nn TORR PDRA-CEC O.OOO 300.0 500 O TORR

Alarm parameter setting ( temperature )

IDENTIFICATION LOU) L H HH HIGH UNIT

TLRCA-PD 523.0 523. O 553.0 733.0 733,0 K TLRCA-JCR1 723.0 723. O 753.0 873.0 873.0 K TLRCA-CT1L 193.0 373.0 K TLRCA-CT2L 330.0 373.0 K TLRCA-CT3L 193.0 373.0 K TRCA -CECIN 343.0 K TLRCA-CECA 823, Q 823. O 873.0 1093, 1093. K TLRCA-CECB 823.0 823.0 ..873.0 1093, 1093. K TLRCA-CECC 823.0 823.0 873.0 1093. 1093. K TLRCA-CECD 823.0 823.0 873.0 1093. 1093. K TLRCA-CECE 823,0 S23.0 873.0 1093. 1093. K TLRCA-CECF 823.0 823.0 873.0 1093. 1093. K TLRCA-0CR2 423.0 &23.0 623.0 K TRCA -0CR2EX 333.0 K TLRCA-ZCB1 698.0 698.0 K TLRCA-ZCB2 698.0 698,0 K TLRCA-ZCB3 698.0 698,0 K

Alann parameter setting ( others)

IDENTIFICATION LOU) L H HH HIGH UNIT

VLRA-UECE HLRA-CTEX HLRA-CECEX RRA -TOTUIT ORA -JCR1IN ORCA-JCRiEX 0. 100

12.00|

100.0

M 10OO.

VOLT KDP KDP CI/M3 % %

VLRA-UECE HLRA-CTEX HLRA-CECEX RRA -TOTUIT ORA -JCR1IN ORCA-JCRiEX 0. 100

197.0 313.0 50,00. 5.000*

100.0

M 10OO.

VOLT KDP KDP CI/M3 % %

U i

21 —

JAE悶 -M93-0印

Table 3.2 Alarm setting situation

Alarm parameter scuing ( prcssurc )

「ーーー・

IDENTIFIC内TION LOW L H HH HIGH UNIT

PR向 -RT1 Z5Q....Q ~ 2.5.Q...Q TORR PRC白-RT2 l..QQ.....Q 2弓Q.....Q TORR PRC向-PDEX ~ TORR PR白・ZCB1EX ~ ~ TORR PRC向・ZCB2EX L5Q....Q ~ TORR PR白 -SCROLIN 12.......Q2 TORR PRC向-ISSIN Z弓Q.....Q 65Q.....!! a.5Q....Q PRC向-JFCUEX L5Q....Q f!5Q....Q TORR PR向ー n~PEX ~ ~ TORR PDR白-CEC ~ ~ 5QQ.....Q TORR

Alann parameter seuing ( temperature )

IDENTIFIC向TION LOW L H HH HIGH υNIT

TLRC白-PD 弓~ 52可 Q 5.5.3.......Q U3......Q l..3可♀ K TLRC向-JCRl Z2.3......Q z2.可 Q ~ 8l..3...J2 8..U......Q K TLRC舟ーCT1L 1.9.J.......Q 3.z..3......!l K TLRC向・CT2L ~ 3.z..3......!l K TLRC白-CT3L 1.9.J.......Q 3.z..3......!l K TRC向・CECIN 2垂勺L....Q K TLRC向ーCEC向 a2L.Q az可 Q al..3.....Q ~ ~ K TLRC内・CECB a2L.Q an....Q al..3.....Q 1Q9..3 ~ K TLRC向“CECC an....Q an....Q al..3.....Q 1Q9..3 ~ K TLRC向ーCECD 82..3.....Q 6.n.....Q all...Q 1Q.9..3 1.Q9.3.. K TLRC向・CECE a2L.Q an....Q al..3.....Q ~ 1.Q9.3.. K TLRC向・CECF ~ a.2.3.......Q al..3......Q ~ ~ K TLRC向・JCR2 垂~ ~ TRC内 -JCR2EX ll3.......Q TLRC向・ZCBl 岳~ 岳9.s.......Q

TLRC向・ ZCB2 ~

ミlTLRC角-ZCB3 岳~ fd..a....Q

Alann parameter se!ting ( others)

IDENTIFIC向TION LOW L H HH HIGH UtHT

VLR向・ωECE 12 QQI VOLT HLR向・CTEX 19.Z.......Q KDP

HLR向-CECEX :ll.J....Q KDP

RR向 -TOTWT ~~ 1..Q..Q.....Q 1.Q.QQ.. C!lM3

OR向・JCRlIN ~

¥↑ 3五

ORC向・JCR1EX !l.-1.QQ ?五

... . -・-

- 21ー

JAERI-M 93-080

Time (hours)

JFCUHCTEX JFCU-H-CECIN JFCU-H-JCR1EX

BEGIN: 06/27/91 14:00:00 END: 06/28/91 14:00:00

Fig. 3. 1 Humidity fluctuation around Cold Traps (CTs) ( JCRIEX is the inlet of trapping CT, CTEX is the outlet of

trapping CT and CECIN is the outlet of regenerating CT.)

u

10 12

Time (hours)

JFCUIWECE BEGIN: 06/27/91 14:00:00 END: 06/28/91 14:00:00

Fig. 3. 2 CEC water decomposing situation

22

JAERI-M 93-080

い伊μ

マ，4141TI寸it1414，

n

u

A

υ

n

U

4

M

2

0

苛叫

d

q

d

句

d

2.00

1.80

1.60 o 24 22

ーーーーー- JFCU.H.CTEX

JFCU.H.CECIN

JFCU.H.JCR1EX

Fig. 3.1 Humidity fluctuation around Cold Traps (CTs)

( JCRIEX is the inlet of trapping CT， CTEX is the outlet of

trappi ng CT and C E C I N i s the outlet of regenerating C T.)

20

BEGIN: 06/27/91 14:00:00

END: 06128191 14:00:00

18 16 14 10 12

Time (hours)

2.00 訓。、

1.50

戸、 1.00

〈

亡J

注0.50

U

0.00

帯。500 24 22 20 18 18 14 10 12

Tim日(hours)

日EGIN: 06127191 14:00:00 END: 06/28191 14:00:00

CEC water decomposing situation

- 22-

Fig. 3. 2

一一-JFCυI.WECE

JAERI-M 93-080

Time (hours) JFCUFVACTPU JFCUFPOEX JFCU-F-CECIN

BEGIN: END:

06/27/91 14:00:00 06/28/91 14:00:00

Fig. 3. 3 Flow rates of hydrogen isotopes (VACTPU), CT regeneration ( C E C I N ) . and PD bleed (PDEX)

£

Time (hours)

JFCU-PRT1 JFCUPRT2 JFCUPPOEX JFCUP-JFCUEX

BEGIN: END:

06/27/91 14:00:00 06/28/91 14:00:00

Fig. 3. 4 System Pressures of Tanks ( R T l is at feed of PD and RT2 is at permeate side of PD) and outlet of PD (PDEX) and J -FCU exhaust ( J F C U E X )

— 23

1.00

"'.・

0.80

0.6日(

戸

之Q.. 0.40 匝」vl )

0.20 <lJ

司.... 診 0.00c Lι

-0.20

-0.40

-0.60

-0.80 o 2

ーーーーー・ JFCU.F・VACTPU

JFCU.F.POEX

JFCU.F.Ce.CIN

JAERI-M 93-080

e a 111 12 ]4

Time (hours)

16 ]8 20 22

BEGIN: 06/27/91 14・00:00END: 06尼6/9114:00:00

Fig. 3.3 Flow rates of hydrogen isotopes (V ACTPU). CT regeneration

(CEC IN). and PD bleed (PDEX)

1.00 ・~， o'

0.80

0.60 (

.... L問。ト』〆 0.40

也J.... 2

'" '" <lJ ι自20

0.00・+-..

-0.20 o

--JFCU.P.RTI

JFCU.P阿T2

JFCU.P.POEX

ー四ー_. JFCU.P.JfCUEX

10 12 14 18

Time (hours)

18 20 22

BEGIN: 06127/91 14:00:00 END: 06126/91 14:00:00

Fig， 3. 4 System Pressures of Tanks (R T 1 is at feed of P D and R T 2 is

at permeate side of P D) and outlet of P D (P D E X) and

J-FCU exhaust (JFCUEX)

- 23-

24

24

JAERI-M 93-080

References

1) TSTA design teams, "Tritium Systems Test Assembly; Final Safety Analysis Report", SAR-82-1F, Los Alamos National Laboratory (1982). 2) Yuji NARUSE, Kenji OKUNO, Hroshi YOSH1DA, Satoshi KONISH1, J.L. ANDERSON and J.R. BARTLIT, "Developments of Tritium Technology for Next-Step Fusion Devices under JAERI-DOE(LANL) Collaboration", J. Nucl. Science and Technology. 27(1990)1081-1095. 3) Satoshi KONISHI, Masahiko INOUE, Takumi HAYASHI, Kenji OKUNO, Yuji NARUSE, J.W. BARNES, and J.L. ANDERSON, "Development of the JAERI Fuel Cleanup System for Tests at the Tritium Systems Test Assembly". Fusion Technol..l9 (1991)1595-1600. 4) J.W. BARNES, J.L. ANDERSON, J.R. BARTLIT, R.V. CARLSON, Satoshi KONISHI, Masahiko INOUE, and Yuji NARUSE, "Experiences with a Japanese-American Fusion Fuel Processing Hardware Project", Fusion Technology. 21(1992)262-265. 5) Satoshi KONISHI, Takumi HAYASHI, Masahiko INOUE, Kenji OKUNO, Yuji NARUSE, H. SATO, Hiroshi FUKUI, K. NEMOTO, M. KUROKAWA, J.W. BARNES, and J.L. ANDERSON, Fablication and Installtion of the JAERI Fuel Cleanup System", Fusion Technology. 21(1992)999-1004. 6) Satoshi KONISHI, Masahiko INOUE, Takumi HAYASHI, Sigeru O'HIRA, Tetsuo WATANABE, Kenji OKUNO, Yuji NARUSE, J.W. BARNES, J.R. BARTLIT and J.L. ANDERSON, "Early Experiments of JAERI Fuel Cleanup System at the Tritium System Test Assembly". Fusion Eng. and Design. 18(1991)33-37. 7) Takumi HAYASHI, Satoshi KONISHI, Hirofumi NAKAMURA, Masahiko INOUE, Kazuhiro HIRATA, Kenji OKUNO, Yuji NARUSE, J.W. BARNES, W. HARBIN, R. WILHELM, M. KING, J.R. BARTLIT and J.L. ANDERSON," Resent Tritium Experiments of the JAERI Fuel Cleanup Syatem (J-FCU) at the Tritium Syatems Test Assembly (TSTA)", Fusion Technology. 21(1992)1979-1983.

— 24 —

JAERI-M 93・080

References

1) TSTA dほsignteams.

SAR-82-IF. Los Alamos National Laboratory (1982).

2) Yuji NARUSE. Kenji OKUNO. Hroshi YOSHIDA. Satoshi KONISHI. J.L.

ANDERSON and J.R. BARTLlT. "Dev定lopmenrsofTritium Technology for Next-Slep

Fusion Devices under JAERI-DOE(LANL) Collaborationぺ1.Nucl. Science and Technolo!!v.

27( 1990) 1 081-1 095.

3) Saloshi KONJSHJ. Masahiko INOUE. Takumi HA YASHI， Kenji OKUNO. Yuji

NARUSE. J.W. BARNES， and J.L. ANDERSON. "Development ofthe JAERI Fuel Cleanup

Sysiem for Tesls al lhe Tritium Sys旬msTesl Assembly". Eusion Technol..19 (1991 )l595-

1600.

4) J.W. BARNES. J.L. ANDERSON， J.R. BARTLIT， R.V. CARLSON， Satoshi

KONISHI， Masahiko INOUE， and Yuji NARUSE. "Experiences with a Japanese-American

Fusion Fuel Processing Hardwa問 Proje氾t".EusionTechnolo!!y. 21 (1992)262・265.

5) Satoshi KONISHI. Takumi HAYASHI， Masahiko INOUE. Kenji OKUNO， Yuji

NARUSE， H. SATO. Hiroshi FUKUI. K. NEMOTO， M. KUROKAWA. J.W. BARNES.

and J.L. ANDERSON， Fablication加 dInstalltion of the JAERI Fuel Cleanup System".

Fusion Technolo!!y， 21 (1992)999-1004.

6) Satoshi KONISHI， Masahiko INOUE， Takumi HA Y ASHI， Sigeru 0・HIRA，Tetsuo WATANABE， Kenji OKUNO， Yuji NARUSE， J.W. BARNES， J.R. BARTLIT and J.L.

ANDERSON， "Early Experiments of JAERI Fuel Cleanup Syslem at the Tritium Syslem Test

Assembly"， Eusion En!!. and Desi!!n.18(1991)33-37.

7) Takumi HA Y ASHI， Saloshi KONISHI， Hirofumi NAKAMURA， Masahiko INOUE，

Kazuhiro HIRATA， Kenji OKUNO， Yuji NARUSE， J.W. BARNES， W. HARBIN， R.

WILHELM， M. KING， J.R. BARTLIT and J.L. ANDERSON， " Resent Tritium Experiments

of the JAERI Fuel Cleanup Sya舵m(J-FCU) at the Tritium Syatems Test Assembly (TSTA)"，

Fusion Technolo!!y，21(1992)1979-1983.

-24-

JAERI-M 93-080

ATTACHMENTS 1. J F C U operation log .

Day and Time Explanation

-June 26 - LIO, JFCU's GB leak check completed

June 27, 08:00 - Connected tritium sample bottle to JFCU for Tritium leak check 09:00 - Tritium leak check. - Helium supply to pressurize the JFCU line

and Scroll-BP "on" and MBP "on". 10:00 - Completed tritium leak check. No leak was found. 11:00 - Evacuation of JFCU. - Pressure sensors and flow meters and flow

controllers zero calibration. - Oxygen monitors calibration.

14:00 - REF "on" and CT cycle operation start. - RT1-2, Scroll, and BP line evacuation by TMP. - Scroll-BP "on" for tritium load in

15:00 - Started tritium load in to JFCU - GB tritium level was going up and a leak point was found on BP.

16:00 - Finished tritium load in. - Stabilized tritium level in JFCU-GB. - MBP "on". - Re-adjustment of system control set points.

17:00 - Potentiostat "on". 18:00 - Started Helium supply from outside cylinder for CT regeneration.

- Started exhausting to TWT. 19:00 - Checked and watched all component working situations. 21:00 - "Pause" by poor oxygen control program.

- Re-started after manual setting of oxygen flow rate. 22:00 - Re-adjusted the set points of "PRC-PDEX" and "PRC-1SSIN" .

- Started continuous hydrogen isotopes circulation (RT2-RT1-PD-Scroll-BP-RT2). - System was stabilized.

June 28, 00:00 - "Pause" by high tritium cone, at the outlet of CT and re-started 01:00 - Started GC sampling and analysis ( sampling points = #3,#4,#5 ) 02:00 - Changed sampling points to #2,#3,#5. 03:00 - "Pause" by high tritium cone, at the outlet of CT and re-started 06:00 - Stopped "Non-impurity operation"

- Manual "Pause" for start up of impurity (CH4) injection. 08:00 - Re-started "impurity operation" with CH4 impurity ( 50 ml/min ).

- "JFCU SAFETY" program "on" and oxygen control was turned to "auto" by MDAC.

09:00 - "Pause" by poor oxygen control and re-started. 10:00 - Changed CH4 injection flow rate to 30 ml/min. 11:00 - Changed GC sampling points to #4 and #5 for check the CH4

combustion situation. 12:00 - Stopped impurity injection and "impurity operation". 13:00 - Recovered hydrogen isotopes in RT2.

• Stopped Helium supply and changed CT regeneration line to "internal".

- Closed all boundary valves and stopped oxygen supply. - "Pause" by "TSTA SCRAM" signal from MDAC. - Started the dry-up operation after some modify of "JFCU SAFETY" program.

15:00 - Stopped CT cycle operation. 16:00 - Evacuated a small amount of process gas to TWT for shut down of

week end. - All pumps "off and closed all boundary valves and kept all

25 —

JAERI-M 93-080

ATTACHMENTS

1. JFC:U operation 109・

ρiw m

T

JU

H

9u

uve

qu

D --June 26

June 27， 08:00 09:00

10:00 11:00

14:00

J5:00

16:00

17:00 18:00

19:00 21:00

22:00

June 28， 00:00 01:00 02:00 03:00 06:00

08:00

09:00 10:00 11 :00

12:00 13:00

15:∞ 16:∞

Expl加 ation

司L10.JFCU's GB leak check completed

-Connected tritium sample boltle 10 JFCU for Tritium leak check -Trilium leak check. -Helium supply to pressurize the JFCU line and Scrol1-BP "on" and MBP "on". -Compleled Iritium leak check. No 1eak was found. -Evacuation of JFCU. -Pressure sensors and f10w melers and flow conlrollers zero calibralion.

ーOxygenmonitors calibralion. -REF"on"加 dCT cycle operation start. -RTI・2，Scroll， and BP line evacuation by TMP. -Scroll-BP "on" for tritium load in -Started tritium load in 10 JFCU 雌 GBtritium level was going up and a leak poinl was found on BP. -Finished lrilium load in. -Stabilized trilium level in JFCU-GB. -MBP "on". -Re-adjustment of system contro1 set points. -Potentiostat "on". -Started Helium supp1y from outside cylinder for CT regeneration. -Started exhausting to TWT. -Checked and watched all component worki時 situations.-"Pause" by poor oxygen control program. -Re-started after manual setting of oxygen f10w rate. -Re-adjusted the set points of "PRC-PDEX" and "PRC-ISSIN" . -Started continuous hydrogen isotopes circulation (RT2-RT1-PD-Scroll-BP-RT2). -System was stabilized.

ー"Pause"by high tritium conc. at the outlet of CT and re-started -Started GC sampling and analysis ( sampling points = #3.#4.#5 ) ーChangedsampling points 10 #2，#3.#5. ー"Pause"by high tritium conc. at the outlet of CT and re-started -Stopped "Non-impurity operωion" . Manual "Pause" for start up of impurity (CH4) injection. -Re-started "impurity operation" with CH4 impurity ( 50 ml/min ). ー"JFCUSAFETY" program "on" and oxygen control was tumed to "auto" by MDAC.

ー"Pause"by poor oxygen control and re-started. -Changed CH4 i吋ectionf10w rate to 30 ml/min. ーChangedGC sampling points to #4 and #5 for check the CH4 combustion situation. -Stopped impurity injection and "impurity operation". -Recovered hydrogen isotopes in RT2. . StぅppedHelium supply and changed CT regeneration line to "intemal". -Closed all boundary valves and stopped oxygen supply. -"Pau凶l路se"by -Started the dry-up operation after some modify of "JFCU SAFETY" program.

-Stopped CT cycle operation. -Evacuated a small amount of process gas to TWT for shut down of week end.

-AII pumps "off' and c10sed all boundary valves and kept all

-25-

JAERI-M 93-080

component under operation temp.

July 3, 10:00 - Re-started the dry up operation 16:00 - shut down for 4th of July.

- All pumps "off and closed all boundary valves and kept all component under operation temp. (CT heater "off)

July 5, 09:00 - Re-started the dry up operation 12:00 - JFCU computer system shut down for data save treatment 13:00 - JFCU computer warm start and re-started the dry up operation 16:00 - Shut down for week end.

- All pumps "off and closed all boundary valves and kept all component under operation temp. (CT heater "off)

July 8, 09:00 - Re-started the dry up operation 16:00 - Stopped dry-up operation

- Evacuated JFCU system gases to TWT - Cooling components ( system shut down)

July 19, - Preparation for inventory check ( ZCB1 regeneration ) ( putting on PCs to LIO GB, and concerned line evacuation )

July 22, 09:00 - Checked line, valves, cooling water flow and heating parameters. - Evacuated JFCU line.

10:00 - Started ZCB1 heating (regeneration) 11:00 - Started the release of hydrogen isotope gases.

- TPl's pumps "on" 13:00 - Changed the PC bottle. 16:30 - Finished regeneration work and Turned off the ZCB1 heater.

July 23, - line purged to TWT. - PCs were transferred to STF for mass analysis.

— 26 —

July 3. 10:00 16:00

July 5， 09:00 12:00 13:00 16:00

July 8， 09:00 16:00

July 19，

July 22， 09:00

10:00 11:00

July 23，

13:00 16:30

JAERI-M 93-080

component under operation temp.

-Re-started the dry up operation -shut down for 4th of July. -All pumps "off' and closed all boundary valves and kept all component under operation temp. (CT heater "、off河"

-Re-started the dry up opcration ーJFCUcomputer system shut down for data save treatment -JFCU computer warm start and re-started the dry up operation -Shut down for week end. -AII pumps "off' and closed aIl boundary valves and kept all component under operation temp. (CT heater "、Ofi町f'河引"

-Re-started the dry up operation -Stopped dry-up operation ーEvacuatedJFCU system g出 estoTWTーCoolingcomponents ( system shut down )

-Preparation for inventory check ( ZCB 1 regeneration ) ( putting on PCs to LlO GB， and concemed line evacuation )

-Checked line， valves， cooling water flow and heating parameters. -Evacuated JFCU line. ーStartedZCB 1 heating ( regeneration ) ーStartedthe release of hydrogen isotope gases. 四 TPl'spumps "on" ーChanged the PC bottle. -Finished regeneration work and Tumed off the ZCB 1 heater.

-line purged to TWT. ーPCswere transferred to STF for mass analysis.

-26-

JAERl-M 93-080

2. GC analysis resul

Niui-impuiily operation

Time 01:15

Sampling # and Species

#2 H2

#3 U2 4.5ft

#4 H2 2.07 ()2 5.1

#5 02 7.ft Ion eh. -

Time 04:50

Sampling # and Species

#2 H2

#3 H2

#4 H2 02

#5 02 4.8 Ion ch. —

01:54 02:47

13.6

7.7ft

7.6 7.5

06:58 07:37

20.78

14.60

4.0 3.0

— 27 —

03:26 04:11

42.7

32.65

ft.7 7.3

2. GC analysls results

¥川トIlllpUItly ¥Ipcr，tltllt1

lilllじ

討，tJlJpling# ，ind Spc日じ、

#ヲ H2

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#4 H2

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Sampling # and SpCじics

#2 H2

#:. H2

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04:50

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7.76 ヌ2.6ラ

7.6 7.) 。.7 7.ヌ

06:うH 07:37

20.n

14.60

4.0 3.0

- 27-

Impurity operation

JAERl-M 93-080

Time 11:09 11:48 12:28

Sampling # and Species

#4 H2 02 CH4

3.04 5.93 0.14

3.16 3.82 013

3.52 0.10

#5 02 C02 Ion ch.

1.74 3.2 3.1 1.7

Sampling gas pressures

#2 ~ 155 torr #3 ~ 150 ton-#4 ~ 110 torr #5 ~ 60 torr

Standard gas pressure for Calibration

GC1 GC1 GC1 GC2

~ 390 torr ~ 390 torr ~ 390 torr ~ 380 torr

- 2 8 -

JAERl-M 93-080

fmpurity operation

Time 11:09 11:48 12:28

Sampling# and Species

#4 H2 3.04 3.16 ω 5.93 3.82 3.52 CH4 0.14 013 0.10

#5 α 1.74 3.2 3.1 C02 1.7 Ion ch.

司J』

弓

3

A『

4J

#廿#甘#甘#宵

Sampling gas pressures

-155 torr ー150torr -J 10 torr - 60torr

Standard gas pressure for Calibration

GCl : -390 to汀GCl : -390to町GCI : -390to汀GC2: -380 torr

-28-

JAERI-M 93-080

Inventory check result

Input 1) Initial input amount of hydrogen isotopes* = H : 15.1 Nl

D:13.0N1 T:3.87N1( 1.03 gram)

2) Other addition ( as CH4) in 1 gram run = H : ~ 24 Nl ( CH4 = -12 Nl) 3) Other addition in the 2nd regeneration of ZCB1** = H : ~ 19 Nl

Total input amount = ~ 56.0 Nl + ~ 19 Nl = 75 Nl (H=58.1.D= 13.0. T= 3.87)

Recovery 1) First regeneration of ZCB1 = H : 36.2 Nl

D : 19.7 Nl T : 2.33 Nl ( 0.62 gram )

total amount = 58.2 Nl ( using only TP1 pumps for regeneration ) 2) Second regeneration of ZCB 1 = H : 23.5 Nl

D : 2.76 Nl T : 0.17 Nl( 0.045 gram)

total amount = 26.4 Nl ( using JFCU Scroll, Booster pumps and TP1 pumps for regeneration)

Total recovered amount ***= ~ 84.7 Nl ( H= 56.7. D= 22.5. T= 2.5 )

3) Calorimeter analysis of JMSBs = T : (0.104 gram) 4) Recovered tritium amount from JCRl by D2 exchanging = total 0.1 gram 5) Exhaust to TWT = T : (~ 0.04 gram )

Analysis performed on Apr. 6, 90 Estimated value Included stored gas before 1 gram run, because of some lack of complete regeneration after last cold run (D?).

— 29 —

JAERI-M 93-080

3. I nventory check rosult

* ** ***

InpUf 1) InitiaJ input amount of hydrogen isotopes* = H ; ] 5.1 NJ

D: 13.0NJ T: 3.87 Nl ( 1.03 gram)

2) Other addition (as CH4) in 1 gram run = H : -24 Nl ( CH4 = -12 Nl) 3) Other addition in the 2nd regeneration of ZCB 1 ** = H ; -) 9 Nl

Total inout amount = -56.0 Nl + -19 Nl = 75 Nl {H= 58.1. D= 13.0. T= 3.87)

Recゅvery1) First regeneration of ZCB 1 = H : 36.2 Nl

D:19.7Nl T : 2.33 Nl ( 0.62 gram )

total amount = 58.2 Nl (using only TPl pumps fi町 regeneration) 2) Second regen氾rationof ZCB 1 = H: 23.5 Nl

D: 2.76 Nl T: 0.17 N1 (0.045 gram)

total amount = 26.4 NI (using JFCU Scroll， Booster pumps加 dTPIpumps for regeneration )

Total recovered amount ***= -84.7 NI ( H= 56.7. 0= 22.5. T= 2.5)

3) Calorimeter analysis of JMSBs = T : ( 0.104 gram ) 4) Recovered tritium amount from JCR 1 by 02 exchanging = total 0.1 gram 5) Exhaust to TWT = T : ( -0.04 gram )

Analysis performed Qn Apr. 6， 90 Estimated value Included stored gas before I gram run， because of some lack of complete regeneration after last cold run ( D?).

-29-

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lit ?1 tt .ill •/

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wi n i.t •e /l> mol ft IS *7 y r 7 cd

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n. ; j . it. H '- x i] IU P a N / m ' x + ^ - . U ,f. *Mit •y _i — (U J N-m 1 4;- . (ft fl-t * r; / 1- W J / s

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ft ft •iii ••;

'/>. m. II Iff. 7>. f* 'J 7 1- ^ 1- y

min . h . d

I. L t

nj r- •* * i-«i I ' - R l i t W .

eV u

leV = 1.60218x10""J 1 u = 1.66054x10=' kg

» 4 siifcicf/ffcir-jic ffi:ft?ft«'W'/.

ft ft j l i i ;

t x C z 1- u -- A A

/< y b

/< JU bar ii yu Gal * -a 'J - Ci u y h V y R 7 K rad u A re n*

1 A=0.1 nm=10-"'m 1 b=100fm ! =10-"m 2

1 bar=0.1MPa = 105Pa 1 G a l s l c m / s ^ l O ^ m / s ' lCi=3.7xl0'°Bq 1 R=2.58xio 'C/kg 1 rad = lcGy=10 zGy hrem=l cSv = 10 ! Sv

* 1 5 SI « v l („,';

Ra fts/U. d „ii •-;

1 0 " X * <t E 1 0 ' " ^x 9 p 1 0 " -r 7 T 10" * « G 10' / *" M 10' * U k 10' 'X 7 r h 10' r * d a

10 "• 7" •> d 10 -' -b y -f c 1 0 " ' ') m 10 ' -7 -f "7 a /i 10"" + / n 10 '*' t 3 P i o - ' 5 7 ! A 1- r 1 0 - ' " T 1- a

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2. iiAICUM'V.. /-,Y, T-n>, ^9 9

3. b a r t i , JISTIi«tf*<DM:yj**<Tri45 ftlCfiif) ii2V)i]T zf <l - IC 7 >f l iS t lTf S„

4. EClSlffti'B'Iffitft'ftTlibar, b a r n ^ J ; tf l|fllH:W'P.(iV.J m m H j ! 4 ( l i 2 f f l » f 3 - | | - l c A * l T l ' - 5 „

/j N'(-IO'dyn)

1

9.80665

4.44822

kgf

0.101972

1

0.453592

Ibf

0.224809

2.20462

1

Wi Iff I P a - s ( N - s / m 2 ) = 1 0 P ( * r x ' ) ( g / f C m - s ) )

•fljWilff lm7s=10 4 St<x \--9 D ( c m ! / s )

/t: M P a f = I O b a r ; kg!/cm' a t m mmhgiTorr) Ibf/in H p s i )

1 10.1972 9.86923 7.50062 x 10 J 145.038

>} 0,0980665 1 0.967841 735.559 14.2233

0.101325 1.03323 1 760 14.6959

1.33322x10- ' 1.35951 x 10- ' 1.31579 x 10"' 1 1.93368 x 10"'

6.89476 x 10"' 7.03070 x 10"' 6.80460 x 10 ' 51.7149 1

X J ( = 1 0 ' e r g ) k g f ' i n k W - h c a K , J W £ ) Btu ft • Ibf eV

(1/ +' 1

1 0.101972 2 . 7 7 7 7 8 x 1 0 ' ' 0.238889 9.47813x10" ' 0.737562 6 .24150x10 '" (1/ +' 1 9.80665 1 2.72407x10-" 2.34270 9.29487 x 1 0 " 7.23301 6.12082x 1 0 "

(1. •If

*H lit

3.6 x 10* 3.67098 x i O s 1 8.59999 x 10 5 3412.13 2.65522 x 10" 2 . 2 4 6 9 4 x 1 0 " (1. •If

*H lit

4.18605 0.426858 1 .16279x10 ' ' 1 3 .96759x10- ' 3.08747 2 . 6 1 2 7 2 x 1 0 "

(1. •If

*H lit 1055.06 107.586 2.93072x10-* 252.042 1 778.172 6.58515 x 1 0 J I

1.35582 0.138255 3.76616 x JO"' 0.323890 1.28506x10"' 1 8 .46233x10 '"

1 . 6 0 2 1 8 x 1 0 " 1.63377 x 10"'" 4 .45050x10"" 3 . 8 2 7 4 3 x l 0 ' ! ° 1 .51857x10"" 1.18171 x lO-'" 1

leal =4.18605 J (dHiWJ;)

= 4.184 J miff-)

= 4.1855 J (15 X )

= 4 . 1 8 6 8 J ( f « « S a * )

ff.'Jf-t' l psdAffiiV;)

= 75 kgf-m/s

= 735.499 W

l& Bq Ci s-t m

1

3.7 x l O 1 0

2 . 7 0 2 7 0 x l O " "

1

Gy

1

0.01

rad

100

1

If IS

C / k g R If IS 1

2.58 x 1 0 ' '

3876

1

m Sv r em lii "i i,t

1

0.01

100

1

(86^12/1" 26 H a f t )

/f I MPa( =10 bar! kgflcm' atm mmHg(Torr! lbflin '( psi)

10.1972 9.86923 7.50062 x 10' 145.038

)) 0.0980665 0.967841 735.559 14.2233

0.101325 1.03323 760 14.6959

1.33322 x 10-' 1.35951 x 10"' 1.31579 x 10" 1.93368 x 10"'

6.89476 x 10-' 7.03070 x 10"' 6.80460 x 10" 51.7149

表 I 5IJH， tP/ ，rおよび l~iUfJ tf\/，í

fll ('，杓. ，ic '，~.

3 メートル π3

'i'l 4 u クラム kg

日年 t::1 f'Y白

，ι Ifrt. アンベア A

~J}"{:i~Jtf見 ケルヒン K

物 n :，t モ Jレ mol

jI; !主 カン F ラ eu 一一一一一 一 一 一 一 一、V uli f/j ラジアン rad

:1. f本 flJ ス子ランヲ'ン sr

表 a [，I，HJのI'，科、をもっ SI制I¥[Ir/な

f1t ず1 科、 nじ"りz 他の SI表Ijl.現/" による

j，'，] t佐 数へ Iレ y Hz s

}J ニュ トン N 日】・kg/s'

11. }j !i:; }J ハス力 Jレ Pa N/m'

エ不 Jレギ .iI目 I~. 晶 llt ‘ン."1 - Jレ J N.m

lギ .敗 q、!c¥i 'J ノ W J/s

'IL: ~)(\ ftt ~丘(，:j ず 口ン C A.s

心/，(， '，(]II:. 起i(]}J ホ Jレ 卜 V W/A

f怜 al ?t I，t 7 "(うト F C/V

IU ' パl IJI. オ ム Q V/A

コンダクタンス メーメンス s A/V

磁 c¥i ウェ- ，、 Wb V・s

磁 c¥i 'J; 1E 7 ス フ T Wb/m'

インゲクヲンス ヘンリー H Wb/A

セルシウ A il品lE セルゾウスl立 ℃

jI; c¥i 'レー〆ン 1m cd'5r H{{ 1ft Jレ ク ス Ix Im/m'

欣 暗イ íi~ べ?レル Bq 5-'

R喰 収 線 f，t ヲF レ イ Gy J/kg

線 I，t I，t ンーへんト 5v J/kg

lbf

0.224809

2.20462

M 1([ I Pa's(N目s/m')=10 P(ポア :;()(g/(cm・s))

耐IJ*!il([ I m'/F 10'Str ̂ トヲス )(cm'/s)

国際単位系 (8I)と換算表

表 2 51と併/11される巾似

I'， fll・う}. U!j. 11

lQ. 分. f'y・

~C ~]

min. h. d

表 5 5/l在ν'Il，/t

/IH:.: I!Mi，h nじ'・'J

10'" ヱクサ E

10'" へ 'l

10" テ ブ 1・

JO暗 ギ プJ G

10' メ カ 加1

¥0‘ キ u k

10' ヘクト h

10' ア 力 da

¥0・ ア ユ〆 d

¥0 センチ む了

JO 、 m

10' 7 イヲ口 11

10'当 ナ ノ n

10 " ヒ コ p

¥1γ" フュムト f 10-111 7 a

iiU

1. 1< I 5は r[I~際 111.仇系 J 第 5 1{ti. [同際

!立I，t衡/"j 1985 11'flJi iによる。ただし.I eV

および Iuの制は CODATAの1986年般奨

納によった。

2. 炎4にはri，j'H. /7~. アール.ヘヲテ

ールもftまれているが1I叩，ωIjl/，r.なのでこ

こでは行時した。

3. barは. JI5では流体のlUJを表わす均

合iζ[Ib[り &2の力テゴリーに分航されてい

る。

4. EC[持IIttF!!'li会指令で!;!.bar. barnおよ

び 11自111の1[1./立JmmHgをぷ2のカテコリ

ーに人れている。

エ J(=IO'ergJ kgf'm kW・h cal(，汁1量枝、) Btu ft • Ibf eV オ'レ 0.101972 2.77778 x 10"' 0.238889 9.47813 x 10・ 0.737562 6.24150x 10同

.t: 9.80665 2.72407 x 10"' 2.34270 9.29487 x 10"' 7.23301 6.12082x 10" .

(f 3.6 x ¥0' 3.67098x iO' 8.59999 x 10' 3412.13 2.65522 x 10' 2.24694 x 10"

. 4.18605 0.426858 1.16279 x 10-' 3.96759 x 10"' 3.08747 2.61272x 10"

鮒fgtL 1055.06 107.586 2.93072 x 10・ 252.042 778.172 6.58515 x 10"

1.3.i582 0.138255 3.76616 x JO"' 0.323890 1.28506 x 10' ， 8.46233 x 10"

1.60218x 10'" 1.63377 x 10" '" 4.45050x 10-26 3.82743x 10-20 1.51857 x 10" 22 1.18171 x 10四円

政

射

能

Ci

2.70270 x 10← 11

吸収線川

リァト Jレ[1. L

ン 1 t

，ιr，y.，レト[eV

h;i J'-'['l:.ttll/'): I u

1 eV=1.60218x 10'''J

1 u士1.66054x ¥0ηkg

表 4 51と!もに判定的』こ

維持される中仇

名i 粉、 d己 云J

オンクポストローム A 〆ぜ ン' b ， ....

2レ bar

ガ ，レ Gal

キ 1 Ci

レントゲ Y R

フ ト rad

レ i‘ rem

IA=O.lnm=IO-"m

1 b=100 fm'= 10-" m'

1 baド 0.¥MPa=IO'Pa

1 Gal三 ¥ cm/s'=IO-'mlピ

1 Ci=3. 7x 10 10 Bq

1 R=2.58x 100'C/kg

1 rad = 1 cGy = 10 'Gy

~ rem = 1 cSv = 10 ' Sv

換 '1'): &

rad 照射線川

100

1 cal = 4.18605 J <.i!'IM1，)

~ 4.184 J (熱化学)

= 4.1855 J 05 "CJ

= 4.1868 J ([f.[際法気表)

it:'Jドド 1 PS (仏n;JJi

= 75 kgf，m/s

= 735.499 W

R

3日76

線1，1

I，t 100

rem

(86年 12月初 日現花)