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

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SUMMARY The results of the research activities on System and Safety of Accelerator-Driven Transmutation (ADS) at the Department of Nuclear and Reactor Physics are described in this report followed by the Appendices of the relevant scientific papers published in 2005. PhD and Licentiate dissertations of Marcus Ericsson, Per Seltborg, Christina Lagerstedt and Daniel Westlén (see Appendices) reflect the research mainstream of 2005. Year 2005 was also very rich in international activities with ADS in focus. Summary of conferences, seminars and lecturing activities is given in Chapter 9 Research activities of 2005 have been focused on several areas: 4 system and safety studies of ADS subcritical experiments ADS source efficiency studies nuclear fuel cycle analysis potential of reactor based transmutation ADS fuel development simulation of radiation damage development of codes and methods Large part of the research activities has been well integrated with the European projects of the 5 th and 6 th Framework Programmes of the European Commission in which KTH is actively participating. In particular European projects: RED-IMPACT, CONFIRM, FUTURE, EUROTRANS and NURESIM. Most important results and conclusions from our studies are summarised below. SYSTEM AND SAFETY STUDIES OF ADS: Design and safety studies have been performed of ADS with americium based fuels and lead-bismuth coolant. Three different types of fuels were investigated: Solid solution nitride fuel with zirconium nitride matrix: (Pu,Am,Cm,Zr) 15 N Composite oxide fuel with magnesium oxide matrix (cercer): (Pu,Am,Cm)O2-x – MgO Composite oxide fuel with molybdenum matrix (cermet): (Pu,Am,Cm) O2-x – 92 Mo The inert matrix improve a thermal stability (nitride fuels) and/or to raise the effective thermal conductivity (oxide fuels). The coolant void worth was identified as the major safety issue of these cores. A gas-cooled accelerator-driven system dedicated to transmutation of minor actinides has been designed. Thanks to the excellent neutron economy of the uranium-free fuel employed, the pin pitch to diameter ratio (P/D) could be increased to 1.8. The increased
coolant fraction allows for decay heat removal at ambient pressure. The large coolant fraction further results in a low pressure loss—26 kPa over the core, 35 kPa in total. Thanks to the large P/D, the elevation of the heat exchanger necessary to remove decay heat by natural circulation is just more than 1 m. The absence of uranium in conjunction with the presence of 35% (heavy atom) americium in the fuel results in a low effective delayed neutron fraction and a vanishing Doppler feedback, making subcritical operation mandatory (Appendix 7). SUBCRITICAL EXPERIMENTS Two major subcritical experiments have been in focus in 2005: Yalina-Booster subcritical experiment in Minsk SAD experiment in Dubna The new experimental program at Yalina-Booster was launched during the fall 2005 with a sophisticated 2 zone core: a fast neutron zone and the thermal neutron zone. A series of experiments have been performed: Reaction rates for different detectors at different positions in the core. Pulsed neutron source measurements (PNS). Source jerk measurements (SJ) Noise measurements Measurement of the neutron flux at the periphery of the active core. Experiments were successful in spite of some technical deficiencies which have been noticed and improvement program has been prepared. KTH prepared an IAEA coordinated research program for 2006-2009 focused on Yalina experiment. Integration program of the Yalina experiment with the European Project Eurotrans has been proposed and is under implementation. SAD experiment experienced a major difficulty in 2005 because of the fire accident at the accelerator site. Parallel to reconstruction work at the accelerator an experimental program of integration of SAD experiment into the Domain 2: Experimental Coupling of Accelerator, Spallation Target and Subcritical Core (ECATS) of the Eurotrans Project has been outlined and proposed to be implemented (see Appendix 15). DYNAMICS AND KINETICS OF ADS Studies on Dynamics and Kinetics of ADS together with Source Efficiency studies have been concluded in two PhD dissertations of Marcus Ericsson (Appendix 8) and Per Seltborg (Appendix 9). Major conclusions are: By itself, subcritical operation provides a distinct safety advantage over critical reactor operation, distinguished by high operational stability and additional margins for positive reactivity insertion. For a uranium-free minor actinide based fuel important safety parameters deteriorate. Specific analyses suggest that operation of such cores in a critical state would be very difficult. The studies of unprotected transients indicate that lead-bismuth cooled accelerator-driven reactors can be effective in addressing the low effective delayed neutron fraction and the high coolant void reactivity that comes with the minor actinide fuel, but some supportive prompt negative feedback mechanism might be considered necessary to compensate for a weak Doppler effect in case of a prompt critical transient. Although lead-bismuth features a high boiling point, the work underlines the 5
Page 1 and 2: System and safety studies of accele
Page 3: Preface The research on safety of A
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 and 14: Modellering av de termo-kemiska ege
Page 15 and 16: LIST OF APPENDICES 1. Carl-Magnus P
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
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6.2 THERMOCHEMISTRY OF ADVANCED FUE
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Figure 7.1 Positions of Cr atoms in
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8 DEVELOPMENT OF CODES AND METHODS
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Let us assume the neutron flux is p
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waste repository notes which year t
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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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