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

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12 2. Radiation Damage in Metals Figure 2.4: The figure shows stress-strain curves for ductile and brittle materials. The ductile material will deform plastically until it breaks while the brittle material shows almost no deformation before breaking [11]. materials with a ductile-to-brittle transition, the temperature at which this transition takes place can shift due to irradiation. These effects have complex dependencies on dose rates, material microstructure and temperature. Embrittlement is a safety issue as ductile deformation tends to occur over a longer time giving a slower fracture with a larger chance of discovery (see figure 2.4). At temperatures below the ductile-to brittle transition temperature, (DBTT), the yield stress of a material is larger than the fracture stress. In this region the fracture will be brittle which means that the material will break with very little plastic deformation. The yield stress is more temperature dependent than the fracture stress. As the temperature is increased, the yield stress will become smaller than the fracture stress and the fracture mode of the material will become ductile and undergo plastic deformation before fracturing. For dislocations to move in a material, they need a certain energy to overcome barriers and obstacles. By raising the temperature in the material, the dislocations are given more energy enabling them to pass obstacles in their way. However, irradiating a material introduces more obstacles and
2.3. Primary Damage Evolution 13 Impact energy Brittle fracture Transition Ductile fracture → Temperature Figure 2.5: A general picture of the ductile to brittle transition in bcc metals such as ferritic steels. At low temperatures the material experiences brittle fracture and at high temperatures plastic fracture. In the transition region, both kinds of fracture are seen. When the material is irradiated, the transition region is shifted towards higher temperatures as shown by the arrow. thus the dislocations need more energy to overcome the barriers. Thus the temperature at which the material turns from brittle to ductile is raised i.e. the DBTT is shifted towards higher temperatures as seen in figure 2.5.
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System and safety studies of accele
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Preface The research on safety of A
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coolant fraction allows for decay h
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To dispose the spent fuel as it is
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SAMMANFATTNING Resultaten från for
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Detaljerade analyser av neutronkine
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Modellering av de termo-kemiska ege
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LIST OF APPENDICES 1. Carl-Magnus P
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ABBREVIATIONS AND ACRONYMS EUROPEAN
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FCC Face Centered Cubic - type of a
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1 SYSTEM AND SAFETY STUDIES OF ADS
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pin. The full core void worth was c
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Figure 2.1 The 1180-loading of Yali
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Counts Counts 10 5 10 4 10 3 10 2 1
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Figure 2.4 Ion source interruption
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New 1 g 232 Th, 238 U (ultra pure)
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3.1.2 System descriptions The PDS-X
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4 NUCLEAR FUEL CYCLE ANALYSIS 4.1 E
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will be calculated using MCB, the M
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irradiation, the spent fuel assembl
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4.1.3 Results The calculations has
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4.2 ANALYSIS OF THE SWEDISH NUCLEAR
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Mass [tons] 300 250 200 150 100 50
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5 POTENTIAL OF REACTOR BASED TRANSM
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due to a partial insertion, the inf
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irradiation to maintain the core as
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configuration allowed the reactor t
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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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Page 631 and 632: 46 CHAPTER 5. FAST SUB-CRITICAL COR
Page 633 and 634: 48 CHAPTER 6. DESIGNING A GAS-COOLE
Page 653 and 654: Bibliography [1] T. Ginsburg. Die f
Page 655 and 656: [29] G. Melese-d’Hospital. Perfor
Page 657 and 658: [58] L.A. Lys et al. Gas turbine po
Page 659 and 660: Acknowledgements Even though my wor
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Page 667 and 668: £ ¤¥¦ §¨¨© ¡¢ ¨§¨ ¢¦
Page 669 and 670: List of Papers I. J. Wallenius, P.
Page 671 and 672: Chapter 1 Introduction About 16% of
Page 673 and 674: Figure 1.1: The length and time sca
Page 675 and 676: 2.2. Primary Damage: Vacancies and
Page 677 and 678: 2.2. Primary Damage: Vacancies and
Page 679 and 680: 2.3. Primary Damage Evolution 9 the
Page 681: 2.3. Primary Damage Evolution 11 20
Page 685 and 686: 3.1. Ab Initio 15 The problem is ad
Page 687 and 688: 3.2. Interatomic Potentials 17 wher
Page 689 and 690: 3.2. Interatomic Potentials 19 3.2.
Page 691 and 692: 3.3. Molecular Dynamics 21 be of th
Page 693 and 694: 3.4. The Monte Carlo Method 23 sele
Page 695 and 696: 4.1. Potential Construction 25 func
Page 697 and 698: 4.2. Verification of Potentials 27
Page 699 and 700: 4.2. Verification of Potentials 29
Page 701 and 702: 4.3. Cascades Using Molecular Dynam
Page 703 and 704: Chapter 5 Summary and Outlook Befor
Page 705 and 706: Bibliography [1] http://www.iaea.or
Page 707 and 708: Bibliography 37 [24] P. Olsson, J.
Page 709 and 710: Modeling of chromium precipitation
Page 711 and 712: MODELING OF CHROMIUM PRECIPITATION
Page 719 and 720: etween EAM and FS type of potential
Page 721 and 722: leaving other properties untouched.
Page 723 and 724: 1. Introduction Displacement cascad
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Page 727 and 728: correspondence with the maximum num
Page 729 and 730: however, that only above 20 keV can
Page 731 and 732: 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
Page 809 and 810:
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
Page 835 and 836:
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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