Materials of equipment for reactor plants  V-320 and V-491

Banyuk G.F., Ryzhov S.B.,

Mokhov V.А., Piminov V.А.

International Topical Meeting VVER 2010. Experience & Perspectives01 – 03 November 2010Prague, Czech Republic

Units with VVER-1000

02

Country Number of Units

Russian Federation

7 (VVER-1000/320) + 3 (VVER-1000/small series)

Czech Republic

2 (VVER-1000/320)

Bulgaria 2 (VVER-1000/320)

Ukraine11 (VVER-1000/320)+ 2 (VVER-1000/small

series)

China 2 (VVER-1000/V-428)

Units of AES-2006 design under construction

03

NPP Number of Units

Novovoronezh-2 (V-392М) 2

Leningrad-2 (V-491) 2

Baltic NPP (V-491) (preparation for construction)

2

Main equipment of reactor plant

04

Reactor pressure vessel and top head

Stream generator

Pressurizer

ECCS hydroaccumulator

Pipelines (MCP)

Reactor plant

05

Reactor pressure vessel

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ParameterValue

V-320 V-491

Length, mm 10897 11185

Inner diameter, mm 4150 4250

Wall thickness in the belt line region, mm

192,5 197,5

Mass, t 320 330

Reactor pressure vessel

07

Additional requirements for materials are caused by:the stronger requirements for equipment and high thermal power as compared with those for a commercial Unit: service life (60 years) and life (fuel cycle 8400 h) are extended; primary and secondary coolant (pressure and temperature) parameters

are increased

Reactor pressure vessel

08

Implementation of the measures aimed at improvement of brittle fracture resistance (BFR) of reactor vessels:

 decrease in radiation embrittlement of RPV materials;

 decrease in loads onto RPV under pressurized thermal shocks;

 improved monitoring of changes in RPV material properties.

Reactor pressure vessel

09

Component Grade of steel

RP V-320 RP V-491

Supporting shell.Cylindrical upper and lower shells

15Х2НМФА-А 15Х2НМФА class 1

Shells of nozzle area 15Х2НМФА-А

Bottom head, flange 15Х2НМФА

Ni influence on radiation embrittlement of reactor pressure vessel steelSurveillance testing results and the results of research programs for VVER-1000 RPV materials have shown, that radiation embrittlement essentially depends on the nickel and manganese content

010

0 10 20 30 40 50 60 70 80 90 100 1100

10

20

30

40

50

60

70

80

90

100

110

120

130

TF, o C

Fluence x 1022m-2 (E> 0.5 meV)

VVER-1000 welds with Ni 1.55-1.88% VVER-1000 welds with Ni 1.10-1.21%

Decrease in radiation embrittlement of RPV materials

011

Chemical composition of RPV base metal (supporting and core shells)

Grade of steel(RP type)

Chemical composition, %

C Si Mn Cr Ni MoV

Calc.

15Х2НМФА-А(В-320)

0.13-0.18 0.17-0.37 0.30-0.60 1.8-2.31.0 – 1.5

0.5-0.7 0.10-0.1215Х2НМФА

class 1 (В-491)1.0 – 1.3

Grade of steel (RP type)

Chemical composition, % Cu S P As Co Sb Sn Р + Sb + Sn

No more than

15Х2НМФА-А(В-320)

0.10 0.006

0.008 0.010 0.03 0.005 0.005

-

15Х2НМФАclass 1 (В-491)

0.06 0.007 0,012

Decrease in radiation embrittlement of RPV materials

012

Chemical composition of RPV welds metal (welds of core range)

Welding wire, flux(RP type)

Chemical composition, %

C Si Mn Cr Ni Mo Ti

Св-12Х2Н2МАА,flux ФЦ-16А (В-320)

0.04-0.10 0.15-0.450.65-1.10 1.4-2.1 1.2 – 1.9 0.45-0.75

-

0.45-1.10 1.2-2.0 1.0 – 1.3 0.40-0.75 0.01-0.06Св-09ХГНМТАА-ВИ, flux НФ-18М (В-491)

Welding wire, flux(RP type)

Chemical composition, %Co S P Cu Sb Sn As

No more than

Св-12Х2Н2МАА,flux ФЦ-16А (В-320)

0.02 0.015 0.0120.10

0.008 0.001 0.010Св-09ХГНМТАА-ВИ, flux НФ-18М (В-491) 0.08

Тко of core weld metal: В-320 ≤ 0 0С

В-491 ≤ minus 15 0С

Decrease in radiation embrittlement of RPV materials

013

Decrease in neutron fluenceFluence decrease is implemented due to increase in the RPV diameter and core arrangement (FA placing) with reduced neutron leakageMaximum values of neutron fluence with an energy above 0.5 MeV for various points

  Location

Design data of neutron fluence (F 1023), n/m2

В-320 (40 years) В-491 (60 years)

Core top (supporting shell) 2.44 1.28Base metal in the place of max.

neutron fluence5.7 4.22

Weld No. 2 5.7 4.06Weld No. 3 4.5 3.58

Decrease in radiation embrittlement of RPV materials

014

Tk calculation results

Location

Tk, 0C

В-320 (40 years) В-491 (60 years)

Core top (supporting shell) 42 29

Base metal in point of max neutron fluence 64 55

Weld No. 2 77 69*

Weld No. 3 71 66*

* - without regard for Тко minus 15°С

Decrease in loads onto RPV under PTS

015

Decrease in loads is achieved due to limitation of the minimum water temperature in the emergency core cooling systemDecrease in loads on RPV under PTS

Reactor plant typeTemperature of ECCS water, 0C,

not less than

V-320 10

V-491 20

Improved monitoring of changes in RPV material properties

016

Improvement is achieved due to change in location of surveillance specimen casks. In RP V-320 the surveillance specimen casks were located in the channels of the reactor core baffle. In RP V-491 the casks are placed directly on the inside wall of the reactor pressure vessel in the place of maximum fluence

Monitoring of RPV metal state during operation (surveillance program)Irradiated surveillance sets are located opposite to the core and fixed directly on the RPV wall.

017

Surveillance specimens

Surveillance specimen program for RPV of RP V-491 defines:1.Irradiated sets (materials, number and date of removal).2.Temperature sets (материалы, number and date of removal).3.Test sets.4.Scheme for cutting of specimens.5.Number of specimens for each type of tests.6.Type of specimens.7.Quality Assurance Program.

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Surveillance specimens

019

Basic requirements for fabrication of surveillance specimensSurveillance specimens for in-service inspection of change in RPV metal properties shall be fabricated from: base metal; weld metal; HAZ metal.Billets of the base metal surveillance specimens shall be cut out of the test ring of the standard shells after basic heat treatment.The billets shall be subject to heat treatments under the modes identical to heat treatment modes of the shell, from which the test ring is cut out, in the course of the vessel manufacture.

Surveillance specimens

020

Basic requirements for fabrication of surveillance specimensBillets of specimens of weld metal and HAZ metal shall be cut out of the circular welded sample, made of metal cut from one of the RPV shells.The sample shall be of the same thickness and the same grooving as the RPV welds.

The circular welded sample shall be made under the same modes and using the same welding process and welding materials of the same lots as the tested RPV welds.

The sample shall be subject to the same complex of heat treatments as the RPV welds to be tested.

The first AES-2006 RPV for Novovoronezh-2 NPP was manufactured at the Izhora plant in this year

The second AES-2006 RPV for Novovoronezh-2 is planned in the next year

021

Main coolant pipeline

022

Tubes for manufacture of MCP

Technical conditions TU 108.1197-83 (the Manufacturer - «EUROTUBE GmbH»)

Outer diameter, mm

Inner diameter, mm

Wall thickness, mm

Maximum length, mm

Thickness of cladding layer,

mm

990 850 70 8400 5

1130 990 70 8400 5

Main coolant pipeline

023

MaterialsChemical composition of the base metal of MCP tubes

Grade of steel

Content of elements, %

C Si Mn Ni Mo V S P Cr Cu

10ГН2МФА0.08-0.12

0.17-0.37

0.70-0.90

1.70-2.00

0.40-0.60

not more than

0.04 0.020 0.020 0.30 0.30

Main coolant pipeline

024

MaterialsChemical composition of deposited corrosion-resistant coating 03Х22Н11Г2Б

Content of element, %

C Si S P Cu Co N Mn Cr Ni Nb

not more than1.00-

2.50

17.50-

20.50

8.50-

11.0

0.70-

1.000.05 1.00 0.02 0.03 0.30 0.02 0.05

Regulatory requirements

025

Regulations for design and safe operation of nuclear plant equipment and pipings (PNAE G -7-008-89).Regulations for strength calculation of equipment and pipings of nuclear power plants (PNAE G -7-002-86).Equipment and pipings of nuclear power plants. Welding and cladding. General provisions (PNAE G -7-009-89).Equipment and pipings of nuclear power plants. Welded joints and claddings. Rules of inspection (PNAE G -7-010-89).

Regulatory requirements

026

 Guiding technological document. Equipment and pipings of nuclear power plants. Welding, cladding and heat treatment of welded joints of components of steels of grades 10ГН2МФА, 10ГН2МФАЛ, 15Х2НМФА, 15Х2НМФА-А, 15Х2НМФА class 1 (RTD 2730.300.02.91).

Standardized control procedures for inspection of base materials (semi-products), welded joints and claddings of nuclear power plant equipment and pipings:

Ultrasonic test. Inspection of base materials (semi-products) (PNAE G -7-014-89).

Magnetic particle test (PNAE G -7-015-89).

Visual and measurement check (PNAE G -7-016-89).

Regulatory requirements

027

Radiographic examination (PNAE G -7-017-89).

Penetrant test (PNAE G -7-018-89).

Check of leak-tightness. Gas and liquid methods (PNAE G -7-019-89).

Ultrasonic test. Part II. Inspection of welded joints and claddings (PNAE G -7-030-91).

Standardized control procedures for inspection of base materials (semi-products), welded joints and claddings of nuclear power plant equipment and pipings

Ultrasonic test. Part III. Measurement of thickness of monometals, bimetals and corrosion-resistant coatings (PNAE G -7-031-91).

Ultrasonic test. Part IV. Inspection of welded joints of austenitic steels (PNAE G -7-032-91).

Welcome to the 7th International Scientific and Technical Conference “Safety Assurance of NPP with VVER” which will take place at

OKB “GIDROPRESS”, Podolsk, Russia on 17-20 May, 2011More details at www.gidropress.podolsk.ru

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THANK YOU FOR YOUR ATTENTION

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