nuclear research institute rez, czech republic sphinx liblice, april 9-12, 2012 1 experimental...

Prezentace aplikace PowerPointSPHINX
by
SPHINX
Project
and
1
SPHINX
1939 discovery of the atomic nucleus fission reaction
1942 first nuclear reactor (solid natural uranium) started by Enrico Fermi team
1943 scientists warned to use the concept of solid fuel and U-Pu fuel cycle in global (industrial) scale, recommended to shift to concept of fluid fuel and Th-U fuel cycle
1950 Aircraft Nuclear Propulsion Program (MSR)
1954 first MSR 2,5 MW in ORNL, USA
1954 first nuclear power station 5 MW in Obninsk, Russia
1957 first commercial PWR (60 MWe) in Shippingport, USA
1960 MSRE in ORNL reached critical state
1965-9 MSRE reached 8 MW
1970 MSBR shifted to Th-U cycle
1972 project of MSR 1000 MW
1979 Three Mile Island NPS crashed, nuclear laws of president J. Carter
1989 renaissance of ADS transmuter
1992 ADS in combination with MSR (Dr Charlie Bowman in LANL)
1995 Drs Nuyi (China) and Hron (Czech Rep.) participated in Dr Ch. Bowman team
Nuclear Research Institute Rez, Czech Republic
SPHINX
Basic Concepts of MSBR
Ø Autonomous Critical MSBR
Ø Subcritical MSBR with External Neutron Source (Accelerator + Target) – ADS, ADTT
Ø Subcritical Inserting Zone (Incinerating and/or Breeding Channel) Inserted into Driving Core (e.g. WWER or FR)
SPHINX
SPHINX
136 mm
236 mm
Enrichment (U235)
SPHINX
*
x[mol%] LiF+y [mol%] BeF2 +z [mol%] NaF + u [mol%] ZrF4 + w [mol%] (HN) F4
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
Principle properties of the BC1100
inserting zone
SPHINX
) = 43,70 m
) = 50,00 m
) = 49,55 m
SPHINX
*
The 1100 inserting zone while charged into the LR-0 driving core
SPHINX
- double purpose MSR
WWER-1000 fuel assembly
molten fluorides of non-fissionable metals (fission products or thorium)
80 mm
SPHINX
*
Radial Distribution of Neutron Group Fluxes in the SR-0 Elementary Module
Graf4
0
0
0
30
30
30
51
51
51
77
77
77
103
103
103
129
129
129
189.5
189.5
189.5
206
206
206
236
236
236
266
266
266
282.5
282.5
282.5
343
343
343
472
472
472
WWER-1000
fluorides
graphite
graphite
fluorides
I
P2
P1
P3
P4
P5
P6
P7
P8
P9
P10
P11
P12
0,5 eV
0,01 MeV
1 MeV
r [mm]
[rel.values]
Radial distribution f neutron group fluxes in the elementary module of the transmuter SPHINX (EROS 5)
2.9
1824
252
3.1
1841
257
5
1885
262
19
2029
273
167
2380
302
518
2792
309
554
3287
449
246
3123
569
127
3138
647
439
3539
749
1247
3834
805
2687
4594
1258
2089
3623
1367.7288255958
Graf1
0
0
0
445
30
30
30
452
51
51
51
466
77
77
77
487
103
103
103
545
129
129
129
602
189.5
189.5
189.5
206
206
206
236
236
236
266
266
266
282.5
282.5
282.5
343
343
343
472
472
472
WWER-1000
fluorides
graphite
graphite
fluorides
I
P2
P1
P3
P4
P5
P6
P7
P8
P9
P10
P11
P12
r [mm]
[rel.values]
2.9
1824
363
252
3.1
1841
366
257
5
1885
371
262
19
2029
395
273
167
2380
460
302
518
2792
503
309
554
3287
814
246
3123
923
127
3138
1101
439
3539
1361
1247
3834
1527
2687
4594
2754
2089
3623
3114
0,5 eV
0,01 MeV
1 MeV
r [mm]
[rel.values]
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
List1
0
40
50
80
110
120
180
200
240
280
300
360
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0,5 eV
0,01 MeV
20 MeV
r [mm]
[rel.values]
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
SPHINX
*
FANTOM for the irradiation by hard spectrum of the NG 2 neutron generator
SPHINX
Graf2
0
0
0
472
64
64
64
343
90
90
90
282.5
129
129
129
266
171.25
171.25
171.25
236
236
236
236
206
282.5
282.5
282.5
189.5
343
343
343
129
103
77
51
30
0
fluorides
fluorides
graphite
graphite
1.37047
3271.36
536.65
1
3.68712
2852.92
306.531
1
12.5182
2812.76
276.711
1
36.8194
2768.15
263.556
1
45.9929
1634.56
173.235
1
16.9926
1547.13
157.86
1
30
1500
170
1
20
1400
140
1
1
1
1
1
1
List1
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
List2
1.37047
3271.36
536.65
1
3.68712
2852.92
306.531
1
12.5182
2812.76
276.711
1
36.8194
2768.15
263.556
1
45.9929
1634.56
173.235
1
16.9926
1547.13
157.86
1
30
1500
170
1
20
1400
140
1
1
1
1
1
1
P2
P1
P3
P4
P5
P6
P7
P8
P9
P10
P11
P12
Radial distribution f neutron group fluxes in the elementary module of the transmuter
SPHINX (EROS 5)
WWER-1000fluoridesgraphitegraphitefluorides
I
P2P1P3P4
P5
P6
P7P8P9P10
P11
P12
MBD000B8BBA.xls
Graf1
0
0
0
445
30
30
30
452
51
51
51
466
77
77
77
487
103
103
103
545
129
129
129
602
189.5
189.5
189.5
206
206
206
236
236
236
266
266
266
282.5
282.5
282.5
343
343
343
472
472
472
WWER-1000
fluorides
graphite
graphite
fluorides
I
P2
P1
P3
P4
P5
P6
P7
P8
P9
P10
P11
P12
r [mm]
[rel.values]
2.9
1824
363
252
3.1
1841
366
257
5
1885
371
262
19
2029
395
273
167
2380
460
302
518
2792
503
309
554
3287
814
246
3123
923
127
3138
1101
439
3539
1361
1247
3834
1527
2687
4594
2754
2089
3623
3114
r [mm]
[rel.values]
List1
0
40
50
80
110
120
180
200
240
280
300
360
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0,5 eV
0,01 MeV
20 MeV
r [mm]
[rel.values]
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
SPHINX
AHTR Test Assembly supplied
The design of the test assembly is a hexagonal block with a pitch of 23.6cm with 19 channels drilled for uranium pins surrounded by salt.
Fuel pins are .753 cm diameter (without cladding) 3.6% enriched and clad with zirconium alloy.
Initial design uses 60% natural LiF and 40% NaF salt. Subsequent experiments will use prototypical salt composition
Hexagonal Array assures us of exact geometry which is critical for an experimental benchmark
SPHINX
*
The BC-1900g (19 graphite assemblies with cylindrical channels filled in by graphite spheres) should be supplied in 2009
PWR
SPHINX
E01 Static Experiments with Various Fluoride Compositions
at Room Temperature 2012-13
Flowing of Fluid Fuel by Movement of Blocks Containing
Fluoride Compositions 2013-14
(by Electric Heating) Salts at Temperatures up to 250oC 2014-15
E04 Static and Dynamic Experiments with Cirulated Molten
(by Electric Heating) Salts at Temperatures up to 650oC 2015-16
SPHINX
SPHINX
2.10 9 years ago
Natural Nuclear Reactors in Oklo (Gabon) Supposed isotopic composition of Uranium 2.10 9 years ago
Age of the Earth [billions of years]
Ratio of number of atoms U 5 and U 8
years
years
nowadays
SPHINX
*
~Half of the elements heavier than Iron (including the Rare Earths) form gradually in Large Stars in the course of stellar lives:
Slow rate of adding neutrons to a nucleus
Able to build elements only up to Bismuth
However a Supernova’s huge neutron bursts synthesize during the first ~15 minutes of Supernova Detonation:
~Half of All Elements Heavier than Iron that exist
All of the Actinides and other Heavy RIs (RadioIsotopes)
Once blasted deep into Space, many RIs & Actinides undergo Spontaneous Fission:
Enriches planet-forming Stardust with additional
Rare Earth Elements
Kim L Johnson ChemInnovar 01 Nov 2010
*
The Sustainable Chemistry & Energy of Thorium
*
SPHINX
REEs: "Chem. Magnets" for Thorium
Early Molten Earth crystallized from the base of the Mantle upward.*
Because REEs couldn’t co-crystallize along with the main silicates of the Mantle (Ca-Mg-
Fe+2 -SiO3), Rare Earths were forced – while yet molten – ever closer to the thin new Crust.
During the journey upward, the migrating REEs gathered (via similar physical chemistry) and pulled along practically all of the mantle’s Thorium and much of its Uranium, heavy Alkali Metals (K/Rb/Cs) and other metals that couldn’t crystallize easily with the Mantle.
Before 30 Ma old, the Mantle began crystalliz-ing into different phases (various blue shades). Also forming just beneath the thickening new Crust was a separate, still-molten phase, highly enriched in REEs.
This REE-Rich Region is shown in Red in Figure (A).
Some time after ~30 Ma however, Earth’s primordial crust cooled, lost buoyancy and began to subduct into the now-solid Mantle (nevertheless still plastic and able to flow)
The subducting Crust dragged Earth’s early REE-Rich Region, now solidified and strongly adhering, deep into the Mantle.
Kim L Johnson ChemInnovar 01 Nov 2010
*
Ref: http://www.physicstoday.org, Mark Wilson, “Boyet and Carlson Made Simple,” September 2005
*
SPHINX
*
Most likely location today for Earth’s early REE-Rich Region
is the Core-Mantle Boundary. Labeled by geologists D” (double-prime), REE-Rich D” reportedly:
Lies ~2700 km under the Crust, resting atop the Iron Core.
Contains ~40% of Earth’s Inventory of REEs and R.I.s (RadioIsotopes).
Generates ~9 TW of Heat (~¼ of that which leaves Earth’s interior). This makes D” the most Thermogenic Structure within the Earth. Averaging ~200-km thick, each area of D” deforms in response to what the Mantle above is doing: Subducting Tectonic-Plate Mantle (cooler, sinking Green material of Fig. B) make regions of D” lying below the slabs thinner and thus cooler.
Mantle Plumes (hot, rising zones under Hawaii, etc) stretch the height of D” beneath. This makes D” under mantle plumes generate even more heat and sustains our planet’s many hot spots with strong convection.
(B) Earth Today
SPHINX
Hongjie Xu, Zhimin Dai
Jialuo Road 2019, Jiading, Shanghai 201800, China
OUTLINE
Nuclear fuelU and Th
Sustainable nuclear fuel supply is the foundation of nuclear power development.
Th and U can be both used to produce nuclear energy but in different routes.
Th is a fertile material so it should be driven by the neutron source produced from the U-based reactor. So utilize of U-based nuclear energy is prior to that of Th.
The deposit of Th is about 3 times more abundant than U on the Earth crust and in China, it is evaluated that Th resources are about 6 times larger than U.
2011-6-20 5
(1)
Natural uranium contains in a small fraction of the fissile isotope U-235(only 0.7%) and much more fertile isotope U- 238. The fission neutrons of U-235 can transmute U-238 into fissile Pu-239.
Natural Thorium only contained fertile Th-232. By absorbing neutrons and after sequential beta decay it can turn into fissile U-233.
Thermal region Fast region
only fast neutron is suitable to
U238/Pu239
Mean released neutron
condition for a sustain
China2010 Slide# : 7
FIRST CONCLUSION –C.Rubia
Unlike other energy sources, China’s reserves of Thorium, may ensure the major domestic energetic supply for many centuries to come.
For instance the whole China’s today electricity (3.2 Trillion kWh/year) could be produced during ≈20’000 years by well optimized Th reactors and 8,9 million ton of Th, a by-product of the China's REE basic reserves.
OUTLINE
Molten salt (fluoride 7LiF-BeF2-ThF4-UF471-16-12-0.3 mol%)is very stable under the radiation of nuetron in MSR.
MSR can operated at atmospheric pressure and high temperature (>700), the safety and nuetron economy have been demonstrated.
Graphite used as moderator is c ongsistent with fluoride salt. The Hastelloy-N have been used as the material of cell,
vessel and other structure succefully. Both fissile and fertile materials are dissolved in high
temperature molten salt, and can be added in succession. The fission products can be extracted and removed from the
reactor online continuously, such as Pa-233 MSR is the first successful operated liquid fuel reactor in the
world and suitable to Th-U fuel cycle.2011-6-20 11
Candidate for Gen IV nuclear energy system
Reactor Neutron spectru
Very High Temperature Reactor(VHTR)
through
Therma l/Fast H2O 510-625
Fuelmaterial thermal hydraulic design
Lead-cooled Fast Reactor (LFR)
Sodium-cooled Fast Reactor (SFR)
waste treatment Selection of advanced recycle systemfuel
Molten Salt Reactor (MSR)
Electricity/hydrogen product/Actinium waste treatment
Fuel reprocessing materialreliability
2011-6-20 13
NE started In Shanghai
NP-D Reactor Physics Experiment Ti-Li reaction mechanism
RC-D Reprocess for MSR
Low-Energy Nuclear Physics Research
Analytical Chemistry RadiochemistryRadio-Medicine
Environment Monitor\Radioactivity Monitor Radioactivity-protection for radioactive-facility
During 1970-1973, SINAP (SINR) built the Zero-power (cold) MSR (1971), and Zero-power LWR (1973) & studied Th232-U233 conversion
History of Th-U and MSR research activities in Shanghai-II
2011-6-20 14
MSR in Tsinghua University
In 1969, Prof. Ying-Zhong Lu of QIng-Hua University, submited a proposal “Advices on investigation of Thorium breeder reactor” to the government. And Nov 1969, the proposal was approved by Prime Minister En-Lai Zhou,.
The feasibility for develop Molten Salt Reactor, High- Tempreature Gas-cooled Fast Reactor, etc. has been researched by the College of Nuclear Research of Tsinghua university.
After about ten year afford , Tsinghua gave up MSR because of the technologies difficulty .
They began to develop High-Tempreature Gas-cooled Reactor from 1980’s
OUTLINE
Nuclear energy medium-long term development plan in China for 2005-2020 (Approved in 2007)
During 2005-2007, serveral proposals on the utilization of Thorium as Nuclear fuel have been submitted to the Government by CAS.
From 2008, Chinese government paied attention to the Thorium utilization, several national-wide meeting have been hold to discuss the technique road of thorium utilization.
From 2009, CAS began to promoted the Thorium-based Nuclear Energy research programm.
Th-U fuel have been one of the new direction of NE in China
2011/6/14 Xu Hongjie 19
Advanced Nuclear Energy Reseach in CAS
Existing Nuclear energy technology in China are mainly imported from several countries. R&D ability should be greatly enhanced in near future, which will concern with not only the reactor technology, but also the fuel-manufacture and waste-disposal (actinide management) .
Under the Central government support, CAS initiated “Innovation 2020” program and deployed Strategetic Pioneer Sci.&Tech. Projects, one of them is “advanced nuclear fission energy of tomorrow”.
The project consists of two parts, TMSR and ADS . First phase of the project (for 5 years) has started from this year.
TMSR ROAD MAP
2011/6/14 20Xu Hongjie
Knowledge mainly from
2015
2020
Of this project 2030
Continue research To solve
TMSR Research Facilities (Basic)in SINAP TMSR Park in new campus
2MW 2MW
2. Molten-Salt Chem. &Eng. 0. supporting
facilities
1.4. Platform of TMSR Design
1.2. Physics of TMSR
1.3. Engineering of TMSR
TMSR WBS(1)---
2.4. Platform of Producing and Refining
2.2.Processing and Refining of Molten Salts
2.3. Circle System and Thermal Engineering Of Molten Salts
2.5. Experimental Platform of Molten Salts Circle System
2. Chemistry and Engineering of Molten Salts
TMSR WBS(1)---
3.4. Wet-process of Fuel
3.3. On-line Dry-process of Molten Salts
3.5. Research Platform of Fuel Circle
3.Radiochemistry and Engineering of Th and U
TMSR WBS(1)---
4.4.Fabricating and Processing platform of Materials
4.2. Structural Materials in TMSR
4.3.Other Materials in TMSR
4. Physics and Engineering of Nuclear Materials
5.1.Nuclear Safety of TMSR
5.2. Radiation Safety of TMSR
5.3. Nuclear Occupational Health and Environmental Evaluating
5.5. Platform of Safety and Environmental Evaluation
5. Nuclear Safety and Engineering
TMSR WBS(1)---
TMSR Site and Research Facilities
Jiading campus of SINAP will become a fundamental research basis of TMSR: (2011~2015) Establish TMSR experiment facility of TMSR as well as
radioactive chemistry, pyrology, material and nuclear security experimrntal facilities , conputation center.
(2016~2020) Continue to develop the ability for basic research of TMSR and expand the conputation center.
New campus away from shanghai 200 km, Nuclear Energy Park will be constructed, and 2MW TMSR experiamtal facility and Radiactive chemitry facility and other TMSR research facilities have been plan to be established coming five years..
TMSR Team TMSR team organized by CAS, leaded by Dr.
Mianheng Jiang, operated by the Center of TMSR , CAS (Director: Hongjie Xu, Deputy: Zhimin Dai).
The staffs come from SINAP, SARI, SIOC, SIC, IMR, CIAC, mainly from SINAP (>90%).
About 700 staffs and 230 graduated students for coming five years.
2011/6/14 28Xu Hongjie
OUTLINE
OUTLINE
(1)
History of Th-U and MSR research activities in Shanghai-I
History of Th-U and MSR research activities in Shanghai-II
MSR in Tsinghua University
Nuclear energy medium-long term development plan in China for 2005-2020 (Approved in 2007)
Slide Number 18
TMSR ROAD MAP
TMSR Team
SPHINX
January 24, 2012
January 25, 2012
U.S. Participants:
Colette Brown, DOE/Office of Nuclear Energy
Jim Bresee, DOE/Office of Nuclear Energy
David Holcomb, Oak Ridge National Laboratory
Terry Todd, Idaho National Laboratory
Jess Gehin, Oak Ridge National Laboratory
Ehud Greenspan, University of California-Berkeley
Benoit Forget, Massachusetts Institute of Technology
Randy Sheele, Pacific Northwest National Laboratory
Thad Adams, Savannah River National Laboratory
Lee Peddicord, Nuclear Power Institute, Texas A&M University
SPHINX
Charles Forsberg (MIT)
Lin-wen Hu (MIT), Per F. Peterson (UCB), and Todd Allen (UW)
Presenter: Benoit Forget (MIT)
Prague, Czech Republic
NEUP - Integrated Research Project
SPHINX
Replace Li-7 by water
External row with graphite and Li-7 to evaluate reflection properties
M.Hron et al, ICAPP 2009
SPHINX
Dear foreign members of ITMSF.
I visited China last month to have meetings with scientists in SINAP
(Shanghai Institute of Applied Physics). As all of you know, China announced to start
the construction of experimental MSRs, starting from zero-powered MSR in 2015,
2MWt MSR, 10MWe(electric)-MSR and 100MWe-MSR. Their approach is very impressive
for me, because there are not only studying ORNL design results, but also they are
investigating related areas in order to know why ORNL made final selection among many
different designs. This approach is to acquire "Know-why", and this is more important thing
than to acquire "Know-how". When I heard their plan in 2010, I was not confident of their
success at first. But, after 5-times meetings with them so far, I became confident of their
success, because of their firm process.
By the way, in last week, I received an invitation letter from India, which says that India
is starting MSR program. India has been studying solid-fuel Thorium reactors long time,
so I was very much surprised by this news. They might recognize that thorium utilization
is best in MSR than in solid-fuel reactor. MSR was in glacial period (ice-freezing period)
for the last 40-years. It is unbelievable that prof. Furukawa has been promoting MSR under
such severe conditions. His heat and effort might break the glacial period. I think we can
declare that "Long-time glacial period ended, or is ending at least". I hope I can inform a good
progress in Japan too.
2012-April-09, Tokyo
SPHINX
Summary-conclusions
The EROS program has been the first step in a complex research of netronic characteristics with specific materials and processes being employed in MSR transmuter as well as Th breeder
In the time being, there have been signed or are under preparation bilateral agreements on a collaboration in the given fields between Czech Republic and some foreign partners (US, Russia, Japan, Australia and probably will be agreed with China in May, 2012 )
*
Project SPHINX is useful for Czech nuclear power program and simultaneously for the international co-operation in that field
On the bases of these agreements the SPHINX Project should be
going on as soon as possible in the favor of the human kind
SPHINX
ATTENTION
Radial distribution f neutron group fluxes in the elementary module of the transmuter
SPHINX (EROS 5)
1
10
100
1000
10000
0100200300400500
fluorides
fluorides

nuclear research institute rez, czech republic sphinx liblice, april 9-12, 2012 1 experimental...

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