thorium msr system-thec12

8/13/2019 Thorium MSR System-ThEC12

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ThEC2012, Shanghai, China, Octo ber 29Nov ember 1, 2012

1

Development of a New Nuc lear Reacto r

Concept w ith Liqu id Fuel Based on Mo lten

Fluor ides for Reducing the Amount and Hazard

o f Nuc lear Waste and an Effect ive Changeover

to Th-U233 Fuel Cycle in the Frame of the

Nat ional Project in the Czech Repub l ic

by

Milo Hron

University of West Bohemia

306 14 Pilsen, Czech Republ ic, e-mai l:[email protected]


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2

Histo r ical roots of the f irst nuc lear era

1939 disco very and prove of the atomic nuc leus f iss ionreact ion

1942 f i rst nuc lear reactor (so l id natural uranium )

1943 warning of sc ient is ts to apply so l id fuel concept andU-Pu fuel cyc le in nu clear power and recommendat ionto sh if t to f lu id fu el concept and to Th-U fuel cycle

1950 Airc raf t Nuclear Propu ls ion Prog ram (MSR)

1954 first MSR 2,5 MW in ORNL, USA1954 f i rst nuclear power stat ion 5 MW in Obnins k, Russ ia

1957 f irst commercial PWR in Shipp ingpo rt , USA

1958 The Phys ical Theory of Neutro n Chain Reactors byAlv in Weinberg and Eugene Wigner issu ed at theUniversi ty of Chicago Press

1963 Phys ical calculat ion of Subcr i t ical Reactor Driven byAc celerator by Milo Hro n, Diplom a Thesis at the CzechTechn ical Universi ty in Prague


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ThEC12 Shanghai, China,Octob er 29Nov ember 1, 20123

Histo ry of MSR in USA

1960 MSRE reached c ri t ical s tate

1965-9 MSRE reached 8 MW

1970 MSBR shifted to Th-U cycle

1972 pro ject o f MSR 1000 MW

1979 Three Mile Island NPS crash

(nu clear laws o f presidentJ. Carter)

1989 renaissance of ADS transmuter

1992 ADS in com binat ion with MSR

(Ch. Bowm an v LANL)Glenn Seaborg and Alvin Weinberg

start up MSRE in ORNL1968


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Histo ry of MSR outs ide USA

1970s sh ift ing of activit ies in

appl icat ion o f MSR to

Japanese pro ject FUJI(MSBR) (Prof. Furu kawa) and

USSR (together with some

Czech inst i tut io ns) project

FREGAT (Pro f. Prusako v)

1995 start ing Czech c ol laborat ion

wi th LANL on ADS conc ept

with MSR

1996 conso rt ium TRANSMUTATION

in the Czech Republ ic h as

been establ ish ed

1997 Czech n ational p rojec t-2008 SPHINX was so lved by the

consor t ium


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Conso rt ium represen tat ive:

Nuc lear Research Ins t i tute Rez plc

SD Nuclear chinery in Pi lsen

Nuclear Physics Institute CS in Rz Czech chnical Universityin Prague

chnical University in Brno (namely i ts

daugh ter EVM Ltd. has associated in

2000)

Univers i ty of West Bohemia in Pilsen

(has asso ciated in 2010)

Col laboratorsmembers of the consor t ium :



Czech National Pro ject SPHINX

(SPent Hot fuel Incinerator by Neutron fluX)

1997 -2000 Pro ject SPHINX 0 (MSR tran sm uter) and

2001 -2004 Project SPHINX 1 Suppo rted by the Czech MIT

2001 -2004 Program o f Ins trum ented Probe BLANKASupported by the Czech RAWRA

2001 -2003 Project SPHINX 1 App roved fo r MOST Project o f5 Frame Work Prog ram o f EU

2004 -2008 Project SPHINX 2 (ThMSR breeder) Suppo rted by theCzech MIT and RAWRA

2005 - 2008 Project SPHINX 2 App roved for MSR SSC GEN IV

1995Intro du ctory Stud ies of Transmutat ion Systems (LANL,ORNL)

1996Czech national conso rt ium TRANSMUTATION Established



Scheme of a MSR transmuterCzech conc ept SPHINX 0 (1997)



Scheme o f the F repro cessing



Fluo rine line FREGAT



Development o f electrochem ical

separat ion techno log ies from

f luo r ide mo lten sal tFor pu r i f icat ion of th e melt from the lanthanides, the

com binat ion of anodic disso lut ion, cathodic

deposi t ion and po ssib ly another pyrochemical

separation techniques h ave to be used



11

System Work ing w i th in the Th U Fuel Cyc le

Czech ConceptSPHINX 2 (2004)


12/49ThEC2012, Shanghai, China, Octo ber 29Nov ember 1, 2012

12

Calcu lated Effect iveness o f the SPHINX

Inc inerator Based on MSR Concept

core c ompos i t ion :35% L iF+38% BeF2+27% NaF +

+ 0.75 mo l %(Pu,MA)F3from PWR Spent

Fuel w ith 40 MWd/kg B urn -up

cyl indr ical homogeneous reactor s ystem w ith a graphi te ref lector

Hfuel=320cm , rfuel=160cm , tgraphite = 50 cm

P=1215MWt, =1x1015cm-2s-1

System Temperatu re 650 C

Negat ive temperature feedback



13

Calculated Masses of Selected Actinides [kg/TWhe]

Actinide PWR SPHINX

Np 1.91x10+0 5.82x10-3

Pu 4.05x10+1 2.39x10-1

Am 1.04x10+0 2.26x10-2

Cm 2.20x10-1 5.24x10-2

Rest Ac t inides in Spent Fuel

%

0.3

0.6

2.2

2.4


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14

Composi t ion of var ious act in ides

masses in spent fuel of PWR and MSRB

PWR

MSRB

Mass

[g]

Optim izat ion of g eom etry o f the SPHINX


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Optim izat ion of geom etry o f the SPHINX

transmuter b lanket elementary module (1997)

R1

R1MAX

1,2

1,3

1,4

1,5

1,6

1,7

1,8

1,9

0 2 4 6 8 10 12 14 16

R1 [cm]

kinf

kinf (100%

kinf (80%)

kinf (50%)

SPHINX 0 (1997 2000) concept


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SPHINX 0 (19972000) concept

exper imental ly proved by EROS

Program(Experimen tal ZeRO

Power Reactor w ith Salt Fuel)

MS liquid

fuel element

graphite

PWR fuel assembly

composition of fluorides

of non-fissionable metals

fuel composit ion

22%UF4+33%LiF+45%NaF

enrichment 100% U235 in UF4

1,6

1,65

1,7

1,75

1,8

1,85

1,9

1,95

0 2 4 6 8 10 12

cylindrical fuel element radius [cm]

k


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Experimental SPHINX 0 Reacto r Concept

Obohacen 35%

0,935

0,94

0,945

0,95

0,955

0,96

0,965

0,97

0 10 20 30 40 50 60

p [cm]

kef

p[cm] kef fuel

composition

0 0.964

7LiF - 33%

NaF - 45%

UF4- 22%

13 0.941

15 0.938

20 0.940

30 0.939

50 0.940

Enrichment 35%U235


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THE LR-0 EXPERIMENTAL


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x[mo l%] LiF+y [mo l%] BeF2+z [mol%] NaF + u [m ol%] ZrF4+ w [mol%] (HN) F4

1. x=y=0; z=100; u=w=0 2. x=100; y=z=u=w=0;3. x=60; y=0; z=40; u=w=0 4. x=50; y=z=0; u=50; w=0

Princ ip le propert ies o f the SPHINX 0

insert ing zone

graphite fluorides

a) b) c)


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Th SPHINX 0 i t i h i l


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The SPHINX 0 insert ing zone wh i le

charged into the LR-0 dr iv ing core

R di l d i t ib t i f t f l


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Radial distribution f neutron group fluxes in the elementary module of the transmuter

SPHINX (EROS 5)

1

10

100

1000

10000

0100200300400500r [mm]

[rel.valu

es]

0,5 eV 0,01 MeV 1 MeV

WWER-1000 fluoridesgraphite graphite fluorides

I

Radial dis t r ibu t ion of neutron g roup f luxes

in the SPHINX-0

elementary module

SPHINX 0 FANTOM modu le fo r i rradiat ion by


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SPHINX 0 FANTOM modu le fo r irradiat ion by

the neutron generator dr iven by cyc lotron

accelerator

operated inNPI CAS

Radial

dist r ibut ion of neutron group f luxes in


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Radial Distribution of Neutron Flux in the FANTOM

1

10

100

1000

10000

0 100 200 300 400 500

r [mm]

F

[rel.values]

FANTOM 0,5 eV FANTOM 0,01 MeV FANTOM 1 MeV

fluorides fluorides graphite graphite

Radial d is t r ibut ion of neutron group f luxes in

SPHINX 0 FANTOM modu le

Global pro ject o f development o f the


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Global pro ject o f development o f the

reacto rs o f the IV generat ion


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26

June 2003: EURATOM incorpo rated in to Generat ion IV

Informat ion Forum

May 2004: Pol icy Gro up GIF decided to establ ished MSR

Steering Comm ittee:

France (Claude Renau lt, CEA Cadarach e)

EURATOM (Milo Hron , NRI Rez)USA (Charles Forsberg, ORNL)

,,,,,,2005: Japan joined MSR Steering

Comm it tee 2006: Russ ia joined w ith i ts concept

MOSART ,,,,,2012: China joined w ith its ThMSRnational program

MSR in the GEN IV Pro jec t

Concept of non -moderated MSR presented at


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27- core volume adjusted to keep the same salt volume

r = 4 cm

r = 8.5 cm

single channel

3 different moderation ratios:

thermal fast

15cm

Concept of non moderated MSR presented at

the EVOL Meeting in Orsay, May 2012

BLANKA L P (2001 4) M i Ai


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28

BLANKA Loop Prog ram (2001-4) Main Aims

Exper imental ver if icat ion of long t ime

behaviour o f t ransm uter blanket wh ich

contains molten f luor ide sal ts as fuel and

graph i te as moderator o r ref lecto r

Material researchbehaviou r of mater ials in

neutron and gamma fields, and mater ia lsinteract ion s on high temperature

condi t ions

Validat ion o f compu tat ional codesby use of

the resu l ts of the irradiated pro bes BLANKA

2.11.2012


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Posit ion H6 of the


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Posit ion H6 of the

BLANKA 1 Rig in the

LVR-15 Research

Reacto r Core

and

Posit ion GH78 of the

BLANKA 4 Rig (B lanketElementary Modu le

Quarter Model) in the

LVR-15 Research

Reacto r Corekartogram

10

9

8

7

6

5

4

3

2

1

A B C D E F G H

B

B

BB B

B

B

B

B

B B

B

B

B

B

B

B B

void

[email protected]

B

B

B

B

:

;

:

:


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The BLANKA 1 r ig scheme

Ins trumented r ig


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BLANKA 1 in the

LVR-15 Research

Reacto r in NRI Rez


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Temperatu res in the BLANKA 1/03 Probe

Measured values by experiment BLANKA 01/2003

0

100

200

300

400

500

600

700

800

900

1000

3.2.2

0031

2:00

3.2.2

0031

4:00

3.2.2

0031

6:00

3.2.2

0031

8:00

3.2.2

0032

0:00

3.2.2

0032

2:00

4.2.2

003

0:00

4.2.2

003

2:00

4.2.2

003

4:00

4.2.2

003

6:00

4.2.2

003

8:00

4.2.2

0031

0:00

4.2.2

0031

2:00

4.2.2

0031

4:00

4.2.2

0031

6:00

4.2.2

0031

8:00

4.2.2

0032

0:00

4.2.2

0032

2:00

5.2.2

003

0:00

5.2.2

003

2:00

5.2.2

003

4:00

5.2.2

003

6:00

5.2.2

003

8:00

5.2.2

0031

0:00

5.2.2

0031

2:00

5.2.2

0031

4:00

5.2.2

0031

6:00

5.2.2

0031

8:00

5.2.2

0032

0:00

5.2.2

0032

2:00

6.2.2

003

0:00

,

BLANKA_T01

BLANKA_T02

BLANKA_T03

BLANKA_T04

BLANKA_T05

Graphi te pots contents in the irradiated BLANKA 1/03


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p p

Melt ing poin ts of the used carr iers

NaF (Tm=995C)

7LiF+NaF (Tm=670C)

Operat ional temperature

To= 850 o C


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Blanket

Elementary

Module

Cylindr ical

Scheme

BLANKA 4 Rig

BLANKA 4 Probe


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graphite

fluorides

aluminum

Fe reflector

air

meas.channels

Simpl i f ied

Model of the

BLANKA 4 Rig

(Quarter Model)

for Neutron ic

Test ing in

Zero Power

Experimental

Reactors

C


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BLANKA 4 Probe

(Elementary Modu le

Quarter Model)

BLANKA 4 Probe Inserted to VR-1Reactor


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at CTU in Prague


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Computat ional

Model of theBLANKA 4

Probe Inserted

in to the VR-1

Experimental

Reacto r Core

Space Dist r ibut ion


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p

of Neutron Flux

in the BLANKA 4

- Well-Thermalized

Neutr ons (E


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temperatu re up to 850 oC

Non-act ive demonstrat ion loop BLANKA 3


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p

SKODA Molten Fluor ide Loops


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MS loop manu factu red by SKODA NM instal led


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and tested in the EVM Ltd . laborator ies

Molten sal t loop proposed for test ing


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in the Labs o f the UWB in Pi lsen

Pre-conceptual


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design o f the

SPHINX 2

demo MSRwith single

(on the left)

and/ordemo MSRB

w i th doub le

pr imary c i rcu i t

(on the righ t)

Summary and Conclus ions


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pro gram Sinc e the very beginn ing of th e 1 nu clear era i t has been warned on a seriour isk connected wi th the sol id fuel concept wo rk ing in U-Pu fuel cyc le in an indu str ialand even more in a massive glob al scale. In th e 50thand 60th, there have been, in USA(ORNL), pract ical ly veri f ied prior i t ies of l iquid fu el for a pos sible closing o f U-Pu cycl

and its advantage for trans fer to Th-U fuel cycle in the 70thand 80th, som e scient i f ic inst i tu t ions in J apan and Russia (together with

Czechoslo vakia) joined th is effort , in th e 90th , a renaissance started in USA (LANL ) anat the beginning o f the 21s tcent ury in EU (2001) and the g lob al pro ject GEN IV (2002)and its MSR SSC (2005)

part ic ipants of MSR SSC (USA, France and EURATOM) has been invo lved in the

development of a ut i l izat ion of molten f luorid es as an effect ive coo lant, MSR in the ro

of breeder for sh i f t ing to Th-U cycle and bu rner of transu ranium (in the year 2005Japan joined it and in 2006 Russia joined it with i ts con cept MOSART and in 2012

China joined with i ts ThMSR national program )

pro gram EROS (Experimental zeRO power Salt reactor) has started, in th e Czech Rep

in the y ear 2007. Now, i t is p roposed to real ize i t in a ful l s cale and und er the

con dit ion s close to operat ional in the frame of internat ional co-operat ion

loop BLANKA s tarted in the Czech Rep. in the year 2001 and there has been performe

a series of act ive pro bes and rigs as wel l as of non -act ive loop s in laboratory up to fu

scale size. Now, i t is prop osed to real ize i t in a ful l scale and under the con dit ion s

close to operat ional in the frame of in ternat ional co-operat ion


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ATTENTION

thorium msr system-thec12

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