System and safety studies of accelerator driven transmutation ... - SKB

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TABLE OF CONTENT SUMMARY 4 SAMMANFATTNING 9 TABLE OF CONTENT 14 LIST OF APPENDICES 15 ABBREVIATIONS AND ACRONYMS 17 OTHER ABBREVIATIONS AND ACRONYMS 18 1 SYSTEM AND SAFETY STUDIES OF ADS 21 2 SUBCRITICAL EXPERIMENTS 24 3 ADS SOURCE EFFICIENCY STUDIES 32 4 NUCLEAR FUEL CYCLE ANALYSIS 35 5 POTENTIAL OF REACTOR BASED TRANSMUTATION 47 6 ADS FUEL DEVELOPMENT 54 7 SIMULATION OF RADIATION DAMAGE 56 8 DEVELOPMENT OF CODES AND METHODS 59 9 INTERNATIONAL INTERACTIONS, SEMINARS, CONFERENCES 65 10 REFERENCES 68 11 APPENDICES 70 14
LIST OF APPENDICES 1. Carl-Magnus Persson, Per Seltborg, Alexandra Ahlander, Waclaw Gudowski, Thomas Stummer, Hanna Kiyavitskaya, Victor Bournos, Yurij Fokov, Ivan Serafimovich, Sergey Chigrinov 2. Carl-Magnus Persson, Per Seltborg, Alexandra Åhlander and Waclaw Gudowski, Sergey Chigrinov, Ivan Serafimovich, Victor Bournos, Yurii Fokov,Christina Routkovskaia, Hanna Kiyavitskaya 3. Alberto Talamo, Waclaw Gudowski 4. Alberto Talamo, Waclaw Gudowski 5. Alberto Talamo, Waclaw Gudowski 6. Alberto Talamo, Waclaw Gudowski 7. Daniel Westlén and Janne Wallenius “Analysis of reactivity determination methods in the subcritical experiment Yalina”, Nuclear Instruments and Methods in Physics Research A 554 (2005) 374–383 “Comparison of neutron kinetic parameters of the subcritical ADS experiments Yalina and Yalina Booster” 12th International Conference on Emerging Nuclear Energy Systems (ICENES’2005) Brussels, Belgium, August 21–26, 2005, on CD-ROM, SCK•CEN, Mol, Belgium (2005) “Performance of the gas turbine-modular helium reactor fuelled with different types of fertile TRISO particles” Annals of Nuclear Energy 32 (2005) 1719–1749 “Comparative Studies of JENDL-3.3, JENDL-3.2, JEFF-3, JEF-2.2 and ENDF/B-6.8 Data Libraries on the Monte Carlo Continuous Energy Modeling of the Gas Turbine-Modular Helium Reactor Operating with Thorium Fuels” Journal of NUCLEAR Science and Technology, Vol. 42, No. 12, p. 1040–1053 (December 2005) “Adapting the deep burn in-core fuel management strategy for the gas turbine – modular helium reactor to a uranium– thorium fuel” Annals of Nuclear Energy 32 (2005) 1750–1781 “Managing the reactivity excess of the gas turbine-modular helium reactor by burnable poison and control rods” Annals of Nuclear Energy 33 (2006) 84–98 “Neutronic and safety aspects of a gas-cooled subcritical core for minor actinide transmutation” Nuclear Technology Vol. 154 Apr 2006 8. Marcus Eriksson “Accelerator-driven Systems: Safety and Kinetics”, Doctoral Thesis, Department of Nuclear and Reactor Physics, Royal Institute of Technology, Stockholm 2005, ISBN 91-7283-988-0 8.1 Marcus Eriksson, Janne Wallenius, Mikael Jolkkonen, James Cahalan 8.2 Janne Wallenius, Marcus Eriksson “Inherent safety of fuels for accelerator-driven systems” Nuclear Technology 151 (2005) 314. “Neutronics of minor actinide burning accelerator-driven systems with ceramic fuel” Nuclear Technology 152 (2005) 367 15
Page 1 and 2: System and safety studies of accele
Page 3 and 4: Preface The research on safety of A
Page 5 and 6: coolant fraction allows for decay h
Page 7 and 8: To dispose the spent fuel as it is
Page 9 and 10: SAMMANFATTNING Resultaten från for
Page 11 and 12: Detaljerade analyser av neutronkine
Page 13: Modellering av de termo-kemiska ege
Page 17 and 18: ABBREVIATIONS AND ACRONYMS EUROPEAN
Page 19 and 20: FCC Face Centered Cubic - type of a
Page 21 and 22: 1 SYSTEM AND SAFETY STUDIES OF ADS
Page 23 and 24: pin. The full core void worth was c
Page 25 and 26: Figure 2.1 The 1180-loading of Yali
Page 27 and 28: Counts Counts 10 5 10 4 10 3 10 2 1
Page 29 and 30: Figure 2.4 Ion source interruption
Page 31 and 32: New 1 g 232 Th, 238 U (ultra pure)
Page 33 and 34: 3.1.2 System descriptions The PDS-X
Page 35 and 36: 4 NUCLEAR FUEL CYCLE ANALYSIS 4.1 E
Page 37 and 38: will be calculated using MCB, the M
Page 39 and 40: irradiation, the spent fuel assembl
Page 41 and 42: 4.1.3 Results The calculations has
Page 43 and 44: 4.2 ANALYSIS OF THE SWEDISH NUCLEAR
Page 45 and 46: Mass [tons] 300 250 200 150 100 50
Page 47 and 48: 5 POTENTIAL OF REACTOR BASED TRANSM
Page 49 and 50: due to a partial insertion, the inf
Page 51 and 52: irradiation to maintain the core as
Page 53 and 54: configuration allowed the reactor t
Page 55 and 56: 6.2 THERMOCHEMISTRY OF ADVANCED FUE
Page 57 and 58: Figure 7.1 Positions of Cr atoms in
Page 59 and 60: 8 DEVELOPMENT OF CODES AND METHODS
Page 61 and 62: Let us assume the neutron flux is p
Page 63 and 64: waste repository notes which year t
Page 65 and 66:
9 INTERNATIONAL INTERACTIONS, SEMIN
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Janne Wallenius Oct 2005 Participat
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[11] Sylvie Pillon and Janne Wallen
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Nuclear Instruments and Methods in
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376 fraction, beff, have been calcu
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378 Fig. 3. Fit of exponentials to
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380 Table 6 Experimental estimation
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382 dominating closer to criticalit
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12th International Conference on Em
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2.2 Yalina Booster Yalina and Yalin
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Yalina and Yalina Booster Λ 1 ⎛
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Yalina and Yalina Booster Table III
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Yalina and Yalina Booster 7 REFEREN
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1720 A. Talamo, W. Gudowski / Annal
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Journal of NUCLEAR SCIENCE and TECH
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1042 A. TALAMO and W. GUDOWSKI Tabl
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1046 A. TALAMO and W. GUDOWSKI 237
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1048 A. TALAMO and W. GUDOWSKI 1) 2
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1052 A. TALAMO and W. GUDOWSKI IX.
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Abstract Annals of Nuclear Energy 3
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Table 1 Technical data of the power
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Abstract Technical note Managing th
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86 A. Talamo / Annals of Nuclear En
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Westlén and Wallenius HEAT REMOVAL
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Accelerator-driven Systems: Safety
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Abstract The accelerator-driven sys
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Acknowledgements I owe thanks to ma
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“A grad student in procrastinatio
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specify the meaning of the term “
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that three fast breeder reactors (F
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emitting properties and its relativ
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TABLE 8 Effective dose coefficients
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Fig. 1 Radiotoxic inventory of the
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prior to disposal. The most commonl
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often used in repository safety ana
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separations process is also known a
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Spent Fuel U Pu PUREX FP + An Np Tc
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Fig. 6 Schematic picture of the pyr
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From the viewpoint of reducing the
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Chapter 3: Transmutation Strategies
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from reprocessing is sent into stor
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adiotoxicity in the spent fuel afte
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In order to overcome the safety iss
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79 Se (T1/2=6.5·10 4 years) and 12
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Source multiplication in a subcriti
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given by the source multiplication
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Fig. 16 Delayed neutron spectra vs.
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offers low void worths. For tight l
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smaller than classical MOX-fuel sur
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Responsiveness of the ADS The kinet
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Fig. 19 compares the response in a
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design parameters. The reference co
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indefinitely. The burst limit is ap
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maintain the reactor in the subcrit
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value (-$18.5), the power increases
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() β ( ) Λ () dck t k t = p t −
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(a) (b) (c) (d) Fig. 25 Source over
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Accelerator reliability In accelera
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Conclusions The thesis analysed and
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Appendix A: Reactor Kinetics Equati
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The definition of F(t) is: ρ () t
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Bibliography 1 R. G. Cochran and N.
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38 M. Bunn, S. Fetter, J. P. Holdre
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75 R. J. Puigh and M. L. Hamilton,
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74 Paper I
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chemical reactions. An “inherentl
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temperature with irradiation time e
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and compressible pool volumes with
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comparison, the FFTF reactor, which
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CerMet and nitride. The reason is t
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failure, which leaves small safety
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XII.B. Transient results The result
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programme,” Nucl. Sci. Eng., Acce
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277, American Nuclear Society, LaGr
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Neutronics of minor actinide burnin
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TABLE I: Fuel Doppler constant KD (
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nitric acid. Therefore, we may not
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(e.g. SS316) on the other hand have
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FIG. 4: Example of core map with 24
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TABLE X: BOL temperature coefficien
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[18] M.A. Smith, E.E. Morris, and R
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76 Paper III
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II. REACTOR KINETICS EQUATIONS In t
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The model pertains to an accelerato
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V.A. Variations in Source Strength
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TABLE VI Calculations of the core c
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pressure, starting at t=1 sec. The
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14. R. E. ALCOUFFE, F. W. BRINKLEY,
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Safety Analysis of Na and Pb-Bi Coo
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Neutronics analysis Table 1. Design
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stoichiometric oxide fuel. The fuel
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4000 3500 3000 2500 2000 Peak fuel
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Figure 7. Sodium (left) and lead/bi
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78 Paper V
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1690 M. Eriksson, J.E. Cahalan / An
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RELIABILITY ASSESSMENT OF THE LANSC
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calculations are based on operation
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Figure 3 is interesting in that sen
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The database is for practical reaso
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Failure analysis Analysis of failur
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Source efficiency and high-energy n
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Abstract Transmutation of plutonium
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The following papers are not includ
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ERALIB1 ERAnos LIBrary ERANOS Europ
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TRU TRansUranic elements TRUEX TRan
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Contents 1 Introduction 1 2 Transmu
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Chapter 1 Introduction The growing
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objectives of the present thesis ha
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n+ 238U → 239U + γ → 239Np + e
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natural uranium is typically needed
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ate step when an even-N nuclide is
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the atomic mass of a specific eleme
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χ (Ε) 0.4 0.3 0.2 0.1 0.0 0 1 2 3
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UOX- LWR 1. Once-through 2. Pu-burn
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2.2.4 Radiotoxicity reduction The t
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onstrated that recovery yields of 9
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advantage, thanks to the radiation
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As was mentioned earlier, a fast ne
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3.3 Coolant options Since the neutr
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3.4.1 Heavy liquid metal target Two
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In a single spallation reaction, ab
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for this purpose, since it allows f
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technical reasons. One is that larg
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concepts, developed by different EU
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Evaluated Nuclear Data Libraries (e
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SATURNE experiments that the Bertin
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4. Number of neutrons appearing as
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The eigenfunctions of hermitian ope
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( , , ) + ∫∫∫ Φ ( , , ) =
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ks FˆΦ FˆΦ = = AˆΦFˆΦ + S ,
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S Fˆ Φ AˆΦ − FˆΦ AˆΦ 1−
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the second-step calculation. This i
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⎛1−kˆ eff ⎞ FΦ ψ * = ⎜
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Moreover, replacing ϕ * ⋅ Z by
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6.3.3 Varying the target radius Bot
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6.3.4 Required proton beam current
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multiplication process from the ext
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Three sub-critical configurations,
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have energy close to 14.1 MeV. Howe
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and can from this point of view be
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1.E+00 Neutron flux (normalised) 10
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7.2.3 Distribution of the spallatio
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equal or slightly larger than 1, wh
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eactivity indicator can be obtained
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Chapter 8 The Yalina experiments In
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8.2 Dynamic experiments performed a
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fundamental decay rate, determined
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ρ n1 − n0 = β n eff 1 . (64) Th
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for this is the fluctuations of the
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above the bottom of the active part
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perimental results. Experience from
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Core power [kW] 300 200 100 0 0 0.9
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29). As expected, it appears that t
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ficients together with the specific
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personnel is 12 µSv/h. However, pr
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High-energy contribution As was sho
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Fig. 46. Vertical cross-sectional v
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there is a fraction of leakage neut
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ψ∗/Ep 40 30 20 10 0 Energy gain
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ψ∗ 40 30 20 10 ZrN matrix YN mat
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Table 20. Proton source efficiency,
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Fig. 56. Horizontal cross-sectional
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Chapter 11 Abstracts of papers 11.1
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11.5 Paper V Different reactivity d
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source response have been investiga
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Table A2. Production facts for oper
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Eq. (B.5) expresses the energy prod
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Table C1 (cont.) Neutrons Photons P
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13 R. Soule, “Neutronic Studies i
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45 H. A. Abderrahim, P. Kuoschus, M
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78 F. Atchison, Proc. of a Speciali
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108 I. Koprivnikar, E. Schachinger,
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The basic idea of ADS is to supply
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equilibrium (Prael, 1998) Models ar
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two dips in the neutron fluxes caus
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4.3 Calculations of ϕ* for the MUS
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Instead of plotting the ratio ϕ* /
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have already been multiplied in the
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APPENDIX A Table 3 Material Composi
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Definition and Application of Proto
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is the best way to define the neutr
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TABLE I Relative Fraction of Actini
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compared to 0.8% for r=50 cm). When
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Proton Source Efficiency ψ * 40 30
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16. L. S. WATERS, “MCNPX TM User
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314 spallation reactions. The produ
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316 current of3.0 mA (1.9 10 13 pro
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318 between 0.1 and 10 MeV, while m
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320 would be very thin, only the un
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322 Relative effective dose 1.E+01
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324 12 mSv h 1 , which is about 15
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326 originates from neutrons with e
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328 [17] Internal SAD document at t
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affecting ψ* - the macroscopic fis
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nected to an increase in ψ*. Preli
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fission and capture cross-sections
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Relative fission probability, σf/(
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F φ >=< Fφ > + < Fφ > + < Fφ >
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tions. Three parameters - the avera
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Nuclear Instruments and Methods in
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fraction, beff, have been calculate
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satisfactory statistical agreement,
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and combining the values of a obtai
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dominating closer to criticality, t
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Abstract Elsevier Science 1 Journal
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adjusted to give a keff close to 0.
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Elsevier Science 5 f Σ Σ c Core F
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Table 6 shows how the differences i
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Transmutation of nuclear waste in g
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ii Abstract The actinides in spent
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iv VI D. Westlén, J. Cetnar and W.
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vi MONJU Japanese experimental fast
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viii CONTENTS 6.5 Summary of the se
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2 CHAPTER 1. BURDENING FUTURE GENER
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10 CHAPTER 2. NUCLEAR REACTIONS Fig
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12 CHAPTER 2. NUCLEAR REACTIONS Fig
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14 CHAPTER 3. FAST REACTORS Reactor
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16 CHAPTER 3. FAST REACTORS reactor
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18 CHAPTER 3. FAST REACTORS Generat
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20 CHAPTER 3. FAST REACTORS Two ent
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22 CHAPTER 3. FAST REACTORS a liqui
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24 CHAPTER 4. PARTITIONING AND TRAN
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34 CHAPTER 5. FAST SUB-CRITICAL COR
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48 CHAPTER 6. DESIGNING A GAS-COOLE
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Bibliography [1] T. Ginsburg. Die f
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[29] G. Melese-d’Hospital. Perfor
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[58] L.A. Lys et al. Gas turbine po
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Acknowledgements Even though my wor
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PROOF COPY [LY8910B] 088545PRB OLSS
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£ ¤¥¦ §¨¨© ¡¢ ¨§¨ ¢¦
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List of Papers I. J. Wallenius, P.
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Chapter 1 Introduction About 16% of
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Figure 1.1: The length and time sca
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2.2. Primary Damage: Vacancies and
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2.2. Primary Damage: Vacancies and
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2.3. Primary Damage Evolution 9 the
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2.3. Primary Damage Evolution 11 20
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2.3. Primary Damage Evolution 13 Im
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3.1. Ab Initio 15 The problem is ad
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3.2. Interatomic Potentials 17 wher
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3.2. Interatomic Potentials 19 3.2.
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3.3. Molecular Dynamics 21 be of th
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3.4. The Monte Carlo Method 23 sele
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4.1. Potential Construction 25 func
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4.2. Verification of Potentials 27
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4.2. Verification of Potentials 29
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4.3. Cascades Using Molecular Dynam
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Chapter 5 Summary and Outlook Befor
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Bibliography [1] http://www.iaea.or
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Bibliography 37 [24] P. Olsson, J.
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Modeling of chromium precipitation
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MODELING OF CHROMIUM PRECIPITATION
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etween EAM and FS type of potential
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leaving other properties untouched.
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1. Introduction Displacement cascad
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(BCA) study [44], to correlate with
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correspondence with the maximum num
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however, that only above 20 keV can
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As explained in what follows, Figs.
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4.2 Clustered fraction While the st
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metals, for example, it has been sh
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Acknowledgements This work required
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[52] W.J. Phytian, A.J.E. Foreman,
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Table 2 - Summary of recoil energie
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Figure captions Figure 1 - Fe-Fe pa
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Number of FP at peak time cascade d
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Number of sub-cascades 4 3 2 1 0 Fi
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SIA clustered fraction Vacancy clus
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SIA clustered fraction Vacancy clus
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* Corresponding author, phone #: +3
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time and the different mechanisms o
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[35]. The use of a large distance c
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SIA clusters have been counted both
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and depleted in SIAs. Isolated vaca
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Figure 3 shows the number of recomb
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potentials predict between 30% and
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To summarize, we expect to see the
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properties. But while in the latter
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[24] H.-E. Schaefer, K. Maier, M. W
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fraction 0.5 0.4 0.3 0.2 0.1 Contri
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Number of defects 20 15 10 5 SIA cl
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Abstract This study is a first step
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Abbreviations ADS Accelerator-drive
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9 ADS and MOX Transmutation Strateg
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Important technological assumptions
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2 Generating nuclear power Fission
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coolants are low neutron capture cr
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steam-generators and other equipmen
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3.3 Conversion At the conversion fa
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3.5.2 Uranium oxide (UOX) The urani
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Table 1. Main elements present in s
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Fig. 4. Fission product yield as fu
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corresponding radioactive decay hal
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4 Swedish Spent Fuel Storage and Di
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Fig. 6. Swedish nuclear waste manag
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handling spent fuel at CLAB. It als
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Secondly it performs an operation o
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6 Nuclear Fuel Cycles studied in th
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7 Advanced Nuclear Fuel Cycles sele
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8 Characterization of the ADS Conce
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9 ADS and MOX Transmutation Strateg
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10.2 Scenario II - LWR + ADS Stabil
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ecycling in Scenario III resulted i
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12 Results - Phase-Out Scenarios 12
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the time of shut-down only 7 tons o
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LWR-park which is doomed to be phas
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22. Working Party on the Physics of
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nuclear power reactor under normal
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fission in LWRs and other reactors
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238 U microscopic cross sections [b
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Appendix B - Transmutation of Nucle
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In a fast neutron spectrum the neut
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understood it is important to exami
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Elsevier Science 1 From Once-throug
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Phase-out Reference Scenario The ph
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varied from 1800 to 3300 [MWt] depe
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plutonium in the system 4 though, w
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Elsevier Science 1 The Subcritical
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3. Subcritical assembly The sub-cri
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6. Conclusion The SAD project is in
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2 2. Key parameters of SAD and supp
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4 Fig. 5 Distributions of the 210 P
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O FFICE PARLEMENTAIRE D ’ ÉVALUA
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Nouvelles Les recherches technologi
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OPECST,Public Hearing, January 20,
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Some pre-declarations for this talk
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Pu can be pretty efficiently (but s
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I am leaving conclusions to the Hon
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System and safety studies of accelerator driven transmutation ... - SKB

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