Thorium MSR System-ThEC12
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Transcript of Thorium MSR System-ThEC12
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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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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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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 :
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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
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Scheme of a MSR transmuterCzech conc ept SPHINX 0 (1997)
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Scheme o f the F repro cessing
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Fluo rine line FREGAT
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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
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System Work ing w i th in the Th U Fuel Cyc le
Czech ConceptSPHINX 2 (2004)
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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
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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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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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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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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
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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