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National Science Center
“Kharkov Institute of Physics and Technology”
National Academy of Sciences of Ukraine
National Academy of Sciences of Ukraine
National Science Center
“Kharkov Institute of Physics and Technology”
Fast Reactor Related Activity
in Ukraine
Sergii Fomin
Akhiezer Institute for Theoretical Physics
NSC “Kharkov Institute of Physics and Technology”
e-mail: [email protected]
46th annual meeting of TWG-FR 21-24 May 2013 IAEA, Vienna, Austria
There are 4 NPP working in Ukraine now, which used 13 WWER-1000
and 2 WWER-440 nuclear power units with total installed capacity of
13,835 MW.
Energy Strategy of Ukraine till 2030
Nuclear Power > 50 % !!!
210,2
251,0
307,0
420,1
101,2 110,5
158,9
219,0
185,2
88,76
0
50
100
150
200
250
300
350
400
450
2005 рік 2010 рік 2015 рік 2020 рік 2030 рік
Всього на АЕС
Annual electricity production in Ukraine in 2005-2030 years, TWh
Total Nuclear
5
Installed NPP capacity (optimistic scenario)
The Ukraine State Program of Fundamental and Applied Researches
on Nuclear Materials and Irradiative Technologies
INSTITUTE OF SOLID-STATE PHYSICS, MATERIALS SCIENCE AND TECHNOLOGIES
(Director - V.N. Voyevodin)
PHYSICS OF RADIATION EFFECTS AND TECHNOLOGIES
New physical notions of the processes of interaction of fast particles andradiations with solids, mechanisms of defect formation and defect structureevolution are originated and developed. Phase transitions in metals, steels andalloys, in semi-conductive and superconductive materials are investigatedunder irradiation in reactor and accelerator conditions.
The theory and methods of rapid simulation of radiation effects occurring inmaterials of nuclear and fusion reactor cores are developed. The efficiency ofuse of high-energy electrons and gamma-quanta (30 - 250 MeV) to simulate theinfluence of reactor irradiation on the mechanical properties of materials issubstantiated and confirmed by experiments.
The methods devised for promoted (100 - 1000 times) study and prediction of thebehavior of materials in fissile cores and fusion reactors through the use ofecologically safe for the environment of high-current charged particleaccelerators and computer simulation allow one to quickly select materials forin-reactor high-dose tests and to reduce by factors of 3 to 5 the time allotted forresearch and development of new materials.
INSTITUTE OF SOLID-STATE PHYSICS, MATERIALS SCIENCE AND TECHNOLOGIES
THE MULTICHARGED ION ACCELERATOR
FOR MATERIALS SCIENCE STUDIES ("ESUVI")
Based on the studies into the influence of dissolved additives and combined effects of
microalloying, high-frequency treatment and radiation-induced processes of
component redistribution and segregation of elements on structural-phase states,
properties and radiation resistance of steels and alloys, the scientists were able:
• to reveal new aspects of a physical nature of radiation-induced phenomena in
materials (swelling, embrittlement, creep, surface erosion, etc.), and thus to direct
the way to increase their radiation stability;
• to justify the possibility for formation and existence of nonsaturated sinks for point
defects in crystal and amorphous materials under irradiation, i.e., the so-called
alternating-polarity point defect recombination centres;
• to discover a new phenomenon of anomalous recombination of radiation defects in
continuously decomposing solid solutions under irradiation;
• to develop methods for calculating and constructing radiation-modified phase
diagrams of alloys at different defect production rates;
• to establish regularities in the evolution of a structural-phase state under irradiation
to high doses in view of cascade mechanisms of dissolution and growth of new
phases, and other factors.
INSTITUTE OF SOLID-STATE PHYSICS, MATERIALS SCIENCE AND TECHNOLOGIES
RADIATION SWELLING OF FERRITIC-MARTENSITIC STEELS
EP- 450 AND HT-9 UNDER IRRADIATION BY METALLIC IONS
TO SUPER-HIGHER DOSES
O.V. Borodin, V.V. Bryk, V.N. Voyevodin, A.S. Kalchenko, Yu.E. Kupriyanova,
V.V. Melnichenko, I.M. Neklyudov, A.V. Permyakov
Swelling of ferritic-martensitic steels EP-450 and HT-9 is studied under
irradiation by Cr ions up to the doses 300 dpa. In temperature range
430F550 ºС parameters of porosity, incubation dose, dose range where
the swelling range reaches the steady state were determined. It was shown
that swelling of ferritic steel may exceed 20 %. The obtained results show
that radiation swelling of ferritic-martensitic steels is the critical parameter
that may considerably limit the commercial use of reactors of Gen 3 and 4.
ЦПАЗННЦ ХФТИ
23nd Meeting of the IAEA Technical Working Group on
Gas Cooled Reactors (TWG-GCR-23)
March 5 – 7, 2013 , IAEA. Vienna, Austria
9
Dr. Mykola Odeychuk
THE DEVELOPMENT OF TECHNOLOGIES OF FUEL
AND COMPONENTS ОF HTGR CORES
National Science Center
“Kharkov Institute of Physics and Technology”
ЦПАЗННЦ ХФТИ
NSC KIPT ADVANCED TECHNOLOGIES
FOR HTGR CORE COMPONENTS
The main technologies - mechanical spheroidization and
gas-phase pyrolytic impregnation - are transformed into
new:
1. Mechanics-vacuum spheroidizing.
2.Gas-phase technology for nitride production with
controlled composition of the gas medium.
3. Gas-phase technology for composites manufacture with
controlled composition of the gas medium.
4. Technology for express simulation radiation tests with
using of charged particle accelerators
ЦПАЗННЦ ХФТИ
TRISO Coated Particle
0.96 mm diameter
15000 coated particles embedded
in GSP Graphite Matrix F
F protected by a 5mm thick
GSP Graphite layer
The final “Pebble” 60mm in
diameter containing thorium
and enriched uranium
NSC KIPT Spherical Fuel
Recent Publications:
M. Odeychuk, Fabrication, properties, in-pile performance and pie of
carbo-nitride and nitride fuels. 1-st Nitride Fuel Workshop, AlbaNova
University Centre Stockholm, Sweden, 01-02 February, 2012, 46 p. -
http://new.neutron.kth.se/NitrideWorkshop/Presentations.
M. Odeychuk, The advanced nitride fuel for fast reactors. IAEA Technical
Meeting on “Design, Manufacturing and Irradiation Behaviour of Fast
Reactors Fuels”, 30 May-03 June 2011, Institute of Physics and Power
Engineering (IPPE), , 2011, 17 p.
M. Odeychuk, The advanced high-temperature fuel for HTGR. AEA TM
“High Temperature Gas Cooled Reactor Fuel and Fuel Cycle“, Vienna,
Austria, September 06-09, 2010, IAEA, Vienna, Austria, 2010, pp. 6; 11; 23. ,
KIPT – ANL Neutron Source Facility
Facility Concept: Experimental Neutron Source Facility based on the use of an electron
accelerator for driving a subcritical assembly with low enriched uranium fuel
Facility Objectives: • Provide capabilities for performing basic and applied research utilizing the
radial neutron beam ports of the subcritical assembly
• Produce medical isotopes and provide neutron source for performing
neutron therapy procedures.
• Support the Ukraine nuclear power industry by providing the capabilities
to perform physics experiments and to train young specialists
National Science Center
“Kharkov Institute of Physics and Technology”
ЦПАЗННЦ ХФТИ
KIPT - ANL Neutron Source Facility
Electron beam power - 100 kW
Electron beam energy – 100 MeV
Neutrons exit from target – 3.28⋅⋅⋅⋅1014 n⋅⋅⋅⋅s-1
Target material – U
Fuel enrichment - ≤ 20 %
Flux - 1.3⋅⋅⋅⋅1013 n⋅⋅⋅⋅cm-2⋅⋅⋅⋅s-1
Allocated capacity in assemblage – 350 kW
KIPT - ANL Neutron Source Facility
Main Components:
• Electron accelerator
• Electron transport channel
• Target assembly for generating neutrons
• Subcritical assembly with low enrichment fuel, carbon reflector,
and water coolant
• Heavy concrete biological shield
• Radial neutron channels for basic and applied research
• Auxiliary equipments including the target and
the subcritical assembly coolant loops
23
№ Parameter Value
1 Electron beam power ~ 100 kW
2 Electron beam energy 150 MeV
3 Target neutron yeld (U/W) 3.28⋅⋅⋅⋅1014/1.91⋅⋅⋅⋅1014 n⋅⋅⋅⋅с-1
4 Target material U / W
5 Fuel 235U enrichment ≤ 20 %
6 Neutron flux near the target ∼∼∼∼ 2.4⋅⋅⋅⋅1013 cm-2⋅⋅⋅⋅ s-1
7 Neutron flux near the reflector ∼∼∼∼ 2⋅⋅⋅⋅1013 cm-2⋅⋅⋅⋅ s-1
8 Maximum fast neutron flux near a fuel, Еn > 0.1 MэВ ∼∼∼∼1.3⋅⋅⋅⋅1013 cm-2⋅⋅⋅⋅ s-1
9 Moderator Н2О
10 Graphite reflector density - 2.3 g⋅⋅⋅⋅cm-3
11 Thermal power absorption in fuel rods ∼∼∼∼ 230 kW
12 Thermal power absorption in reflector ∼∼∼∼ 20 kW
13 Total thermal power ∼∼∼∼350 kW
Main Parameters of the Installation
KIPT - ANL Subcritical assembly (ADS)
Subcritical assembly configuration
indicating four irradiation locations
where the first is close to the center
10−8
10−7
10−6
10−5
10−4
10−3
10−2
10−1
100
101
3e11
4e11
5e11
6e117e118e119e111e12
2e12
3e12
4e12
5e12
Energy [MeV]N
eutr
on F
lux
/ Let
harg
y [n
/s⋅c
m2 ]
1st Location
2nd Location
3rd Location
4th Location
Neutron spectrum in the four-irradiation
locations where the first is close to the
assembly center
Physical Basis of Innovative Fast Reactor
Working in the Nuclear Burning Wave Regime
(“Traveling Wave Reactor”)
Sergii Fomin
NSC “Kharkov Institute of Physics and Technology”
Akhiezer Institute for Theoretical Physics, Kharkov
also
"Nuclear Fuel Cycle" , NSC KIPT, Kharkov
Institute for Nuclear Research of NAS of Ukraine, Kyiv
Taras Shevchenko National University of Kyiv, Kyiv
Odessa Politechnical State University, Odessa
46th meeting of TWG-FR 21 May 2013 IAEA, Vienna, Austria
L.P. Feoktistov, 1988. An analysis of a concept of a physically safe reactor. Preprint IAE-4605/4.
L.P. Feoktistov, 1989. Neutron-fission wave. Sov. Phys. Doklady, 34, 1071.
238U (n,γγγγ) →→→→ 239U (ββββ) →→→→ 239Np (ββββ) →→→→ 239Pu (n,fission) ...
T1/2 ≈≈≈≈ 2.35 days
( )( )2
8 8 Pu2 Pua a f
n nD vn N N
t zσ σ σ
∂ ∂= + − +
∂ ∂
88 8
;a
Nvn N
tσ
∂= −
∂9
8 8 9
1a
Nvn N N
t β
στ
∂= −
∂
( )Pu9 PuPu
1a f
NN vn N
t β
σ στ
∂= − +
∂
x z Vt= +
8 8Pu aeq Pu Pu
f a
NN
σσ σ
=+
( 1)
ai iPu icr Pu
f
NN
σ
ν σ=
−∑
Pu Pu
eq crN N>
Edward Teller (USA, 1997): Traveling Wave Reactor (Monte Carlo simulation: Th-U fuel)
E.Teller, 1997. Nuclear Energy for the Third Millennium. Preprint UCRL-JC-129547, LLNL.
Hiroshi Sekimoto (Japan, 2001): CANDLE (Determ. appr.: 2d stationary problem: U-Pu fuel)
H. Sekimoto et al., 2001. A New Burnup Strategy CANDLE. Nuclear Science & Engineering, 139, 306.
(Analytical approach: 1d stationary problem: U-Pu fuel)
Lev Feoktistov (USSR, 1988): Neutron - fission wave
Goldin & Anistratov (USSR, 1992): (Deterministic appr.: 1d non-stationary problem: U-Pu fuel)
V. Goldin, D. Anistratov, 1992. Math. modelling of neutron-nuclear processes in safe reactor, Preprint IMM RAS # 43.
Necessary condition
!!
1928 - 2002
Our publicationsOur publicationsOur publicationsOur publications: : : :
S. Fomin et al., Annals of Nuclear Energy, 32 (2005) 1435-1456.
S. Fomin et al., Problems of Atomic Science & Technology, 6 (2005) 106-113.
S. Fomin et al., Nuclear Science & Safety in Europe. Springer (2006) 239-251.
S. Fomin et al., Problems of Atomic Science & Technology, 3 (2007) 156–163.
S. Fomin, Reactor Physics and Technics. PINP WS, St-Perersburg, XL-XLI (2007) 154-198.
S. Fomin et al., Progress in Nuclear Energy, 50 (2008) 163-169.
Yu.Mel’nik et al., Atomic Energy, 107 (2009) 288-295.
S. Fomin et al., Progress in Nuclear Energy, 52 (2011) 800-805.
Conference activityConference activityConference activityConference activity: : : :
2005 - ICENES (Brussels, Belgium) IC058; NATO-ARW NSSE (Yalta, Ukraine); IAEA-RCM ADS (Minsk, Belarus)
2006 - ICAPP’06 (Reno, USA) paper 6157; NPAE (Kiev); QEDSP’06 (Kharkov); INES-2 (Yokohama, Japan)
2007 - ICAPP’07 (Nice, France) paper 7499; WS PINP (St-Perersburg, Russia); IAEA-RCM ADS (Roma, Italy)
2008 - Channeling’08 (Erice, Italy); NATO-ARW SNE (Yalta, Ukraine) | NPQCD (Dnepropetrovsk, Ukraine)
2009 - IAEA-RCM ADS (Vienna, Austria), ANIMMA (Marseille, France); Global 2009 (Paris, France) paper 9456
2010 - IAEA-RCM ADS (Mumbai, India); PINP WS (St-Perersburg, Russia); ICAPP (San Diego, USA) paper 10302
NPAE (Kiev); IAEA-TWG-FR (Brussels, Belgium); 19 ICPRPRMS (Alushta, Ukraine); INES-3 (Tokyo, Japan)
2011 - IAEA-TWG-FR (Beijing, China); NSC KIPT SS (Alushta, Crimea); QEDSP’11 (Kharkov, Ukraine);
IAEA-TWG-FR (Chinnai, India); IAEA-TWG-FR (Vienna, Austria),
L z
r
R
L
ign
j ext
Breeding zoneIgnition zone
238 U 100 %238 U
90 %
239 Pu
10 %
2D Non-Stationary Theory of Nuclear Burning Wave
S. Fomin, Yu. Mel’nik, V. Pilipenko, N. Shul’ga, A. Fomin (1st IC “Global 2009”, Paris, paper 9456)
Nuclear Burning Wave
( )/ / / / / /
/ / /
1 1
1
1 1 1
1 1
( ) ( )
g g gg g g g g g g g g g
a in mod in modg
gG Gg g g j j g g j j j g g g
f f f d l f f l d l l inj l j lg g g
rD Dv t r r r z z
Cχ ν χ β ν χ λ
→ − −
−→
= = =
∂Φ ∂ ∂Φ ∂ ∂Φ− − + Σ +Σ +Σ −Σ Φ − Σ Φ =
∂ ∂ ∂ ∂ ∂
= Σ Φ − Σ Φ + + Σ Φ∑ ∑ ∑ ∑ ∑ ∑ ∑
( 1) ( 1) ( 1)
g gg glal l l c l l l
g g
NN N
tσ σ − − −
∂= − Φ +Λ + Φ +Λ
∂ ∑ ∑
Non-Stationary Nonlinear Multi-Group Diffusion Equation of Neutron Transport
Together with Fuel Burn-up Equations and Equations of Nuclear Kinetics
of Precursor Nuclei of Delayed Neutrons
96 6
NN
t
∂= Λ
∂
10
1,4,5,6,7
gg
fl l
l g
NN
tσ
=
∂= Φ
∂ ∑ ∑
( )j
j j j g g gll l l f f l
g
CC
tλ β ν
∂= − + Σ Φ
∂ ∑
Metal fuel (44%)
Pb-Bi coolant (36%)
CM - Fe (20%)
jext ~ 1015 cm-2 s-1
toff = 400 days
( 1 8);, l = ÷
232Th 233Th
233Pa
233U 234U 235U 236U 237U
T½ = 22.2 min
T½ = 27 days
237Np
T½ = 6.75 days
238U 239U
239Np
239Pu 240Pu 241Pu 242Pu 243Pu
T½ = 23.5 min
T½ = 2,35 days
243Am
T½ = 4.98 hours
241Am
T½ = 14,3 years
Th-U fuel cycle
U-Pu fuel cycle
2009: NBW reactor with mixed Th-U-Pu fuel cycle
Example: Metallic fuel 232Th (62%) + 238U (48%) volume fraction = 55%,
fuel porosity p = 0.35; Coolant (Pb-Bi eutectic) vol. frac. = 30%,
Constr. materials (Fe) vol. frac. = 15%; R = 390 cm
L z
r
R
L зап
Jext
Breeding zoneIgnition zone
238 U 50 %238 U
90 %
239 Pu
10 %232Th 50 %
NBW reactor with mixed Th-U-Pu fuel cycle
Example: Metallic fuel 232Th (62%) + 238U (48%) volume fraction = 55%, fuel porosity p = 0.35;
Coolant (Pb-Bi eutectic) vol. frac. = 30%, Constr. materials (Fe) vol. frac. = 15%; R = 390 cm
0 100 200 300 400 500
1
2
3
4
5
6
t7
t6
t5
t4
t3
t2,×0.02
t1
z
Φ
a)
0 100 200 300 400 500
0.2
0.4
0.6
0.8
1.0
1.2
t7
t6
t5t
4t3
t2
t1
z
N
b)0 100 200 300 400 500
10
20
30
40
50
t7
t6
t5
t4
t3
t2
z
B
c)
FIG. 3. the axial distributions (z, cm) of the nbw
characteristics: (a) scalar neutron flux
Φ (×1015 cm-2 s-1); (b) concentration n (×1021 cm-3) for 239Pu (solid curves) and 233U (dots); (c) fuel burn-up
depth b (%) for the fuel components 238U–Pu (solid
curves) and 232Th (dots) for calculation variant 1 for
time moments t1 = 4, t2 = 100 days, t3 = 10, t4 = 30,
t5 = 45, t6 = 60 and t7 = 70 years.
National Academy of Sciences of Ukraine
Nuclear Burning Wave Reactor:
Smooth Start-Up Problem
Sergii Fomin, A. Fomin, Yu. Mel’nik, V. Pilipenko, N. Shul’ga
Akhiezer Institute for Theoretical Physics
NSC “Kharkov Institute of Physics and Technology”
e-mail: [email protected]
IAEA TWG-FR 29 Feb – 2 March 2012 IAEA Vienna
Startup problem of the NBW Reactor
(10-3 b-1cm-1) (10-3 b-1cm-1)
238U/8 238U/8
Pb-BiPb-Bi 239Pu
181Ta
239Pu
Neutron flux Φ, b-1day-1
Smooth Startup of the NBW Reactor
0 100 200 300 400 500 600 700
4
8
12
16
20
24
28
PI , GW
t, days
0 2 4 6 8 10 12 14 16 18 20 22 24
0,5
1,0
1,5
2,0
2,5
3,0
3,5
4,0
PI , GW
t , years
National Science Center
“Kharkov Institute of Physics and Technology”
Mechanism of Negative Reactivity Feedback
in Nuclear Burning Wave Reactor
Sergii Fomin, A. Fomin, Yu. Mel’nik, V. Pilipenko, N. Shul’ga
Akhiezer Institute for Theoretical Physics, NSC KIPT, Kharkov, Ukraine
e-mail: [email protected]
IAEA TWG-FR 2-7 March 2013 FR-13 Paris
ττττ ≈ 2.5 days R = 230 cm
Perturbation of integral neutron flux Fint (×1022 cm/s)
caused by an external neutron source via time t (days)
The source with intensity Qext = 2×1011 (cm-3 s-1)
starts at t0 = 3650 days, lasts during 1 hour
and is situated at а) 160 < z < 170 cm,
b) 200 < z < 210 cm, c) 55 < z < 65 cm.
Negative Reactivity Feedback of the NBW Reactor
-10 0 10 20 30 40 50 60 70 80
5
10
15
20
25
30 a)Φ
int
t-t0
-10 0 10 20 30 40 50 60 70 80
2
4
6
8
10
12
14
16
t-t0
c)
Φint
-10 0 10 20 30 40 50 60 70 80
2
4
6
8
10
12
14
16
t-t0
c)Φ
int
160 < z < 170 cm
200 < z < 210 cm
55 < z < 65 cm
Evolution of the volume-averaged neutron flux Fav (×1015 cм-2 с-1) and concentrations Nav (×1017 cm-3)
of the main fissile and intermediate nuclides in the fuel of mixed ThUPu cycle with time t (days) at the
initial stage of the neutron flux perturbation t0 = 3650 days. The averaged nuclide concentrations: NNp
is for 239Np, NPa = NPa - 53.1·1017 cm-3, is for 239Pu is for 233U.
-1 0 1 2 3 4 5 6 7 8
1
2
3
4
t - t0
Φav
0
1
2
4
5
6
7
8
~
~
NNp
NPa
NPu
NU
~
Nav
Φav
Negative Reactivity Feedback: Stability of the NBW Regime
0Pu Pu Pu 1t
N N N−
= −%
0U U U 1
,t
N N N−
= −%
ττττ ≈ 2.5 days
Variation of the reactivity ρ (dollars) with time t (days)
along the variation of the volume-averaged neutron flux Fav (×1015 cм-2 с-1)
Negative Reactivity Feedback: Stability of the NBW Regime
-1 0 1 2 3 4 5 6 7 8
1
2
3
4
t - t0
Φav
-0,20
-0,15
-0,10
-0,05
0,00
0,05
0,10
0,15
0,20
ρ
ρ Φav
Stability of the NBW Regime
0 10 20 30 40 50
2
4
6
8
10
12
14
16
18
Pint
, GW
t, years
62% Th, R=230 cm, 5% brick, z=300÷320 cm
62% Th, R=230 cm, 10% brick, z=300÷320 cm
Variation of the neutron flux Fav (××××1015 cм-2 с-1) with time t (days) due to the partial
loss of coolant (а) 1% fraction during 0.1 days in front of NBW (270<x<290 см) and
(г) 5% coolant fraction during 0.1 days after the NBW (150<x<170 см)
Coolant loosing NBW reactor behavior
-1 0 1 2 3 41.2
1.4
1.6
1.8
2.0
2.2
2.4a)
Φav
t-t0
-1 0 1 2 3 4
1.6
1.8
2.0
2.2
2.4
2.6
2.8г)
Φav
t-t0
- negative feedback on reactivity - intrinsic safety
- long-term (decades) operation without refueling and external control
- possibility of 232Th and 238U utilization as a fuel
- fuel burn-up depth for both 238U and 232Th ≈ 50%
- neutron flux in active zone ≈ 2·1015 n/сm2s
- neutron fluence during the whole reactor campaign ≈ 3·1024 n/сm2
- energy production density in active zone ≈ 200 W/сm3
- total power at the steady-state regime ≈ 1.2 GW
- wave velocity at the steady-state regime ≈ 2 сm/year
- possibility of nuclear waste burn out (expected)
Main features of NBW reactor with mixed Th-U-Pu fuel cycle
Reactor composition (vol. frac.):
Fuel = 55% (FTh = 62%, p = 0.20), Coolant = 30%, CM = 15%, R = 215 cm
1A-1-2: Sustainable Burning Reactors - Chairs: Kevan Weaver (TerraPower, USA)
Traveling-Wave Reactors: Challenges and Opportunities - Kevan Weaver et al. (TerraPower, USA)
Feasibility of LBE Cooled Breed and Burn Reactors - Ehud Greenspan (UC, Berkeley, USA)
Preliminary Engineering Design of Sodium-Cooled CANDLE Core - Hiroshi Sekimoto (TIT, Japan)
Nuclear Burning Wave in Fast Reactor with Mixed Th-U Fuel - Sergii Fomin et al (NSC KIPT, Ukraine)
Nuclear Traveling Wave in a Supercritical Water Cooled Fast Reactor – W. Maschek (KIT, Germany)
Development and Prospects of TWR Project in China - Zheng Mingguang (Shanghai NER&DI, China)
1A-3: Thorium Fuel Reactors - Chair: Sergii Fomin (KIPT, Ukraine)
(Th-U-Pu) - Mixed Fuel Cycle and Proliferation– E. Kryuchkov et al, (MEPhI, Russia)
Large Scale Utilization of Thorium in Gas Cooled Reactors - V. Jagannathan (Bhabha ARC, India)
INTERNATIONAL ATOMIC ENERGY AGENCYINTERNATIONAL ATOMIC ENERGY AGENCYINTERNATIONAL ATOMIC ENERGY AGENCYINTERNATIONAL ATOMIC ENERGY AGENCY
Nuclear Burning Wave Benchmark Specifications
for the IAEA Coordinated Research Projects
Analytical and Experimental Benchmark Analysis
on Accelerator Driven Systems
& Technical Working Group – Fast Reactors
Compiled By
S. Fomin, Yu. Melnik, V. Pilipenko, N. Shul’ga
Akhiezer Institute for Theoretical Physics
National Science Center “Kharkov Institute of Physics and Technology”
National Academy of Sciences of Ukraine
Issued 2009-03-30