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Nuclear Development ACTINIDE AND FI
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FOREWORD The objective of the OECD/
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TABLE OF CONTENTS Foreword ........
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EXECUTIVE SUMMARY More than 160 par
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identified. In the fuel area, labor
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17:20-19:05 Session III: Partitioni
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Poster sessions Poster session: Par
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WELCOME ADDRESS Lucila Izquierdo Ge
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WELCOME ADDRESS Michel Hugon Co-ord
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WELCOME ADDRESS Philippe Savelli De
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developments. This will surely beco
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use of FBRs for transmutation toget
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view, i.e. better use of uranium an
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W. Forsberg proposes to reduce the
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1. From the open fuel cycle to the
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Figures 2 and 3 show the radiotoxic
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Denoting the transuranic (TRU) or m
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or, in terms of the fuel burn-up an
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quantities of LWR-MOX and FR-MOX wi
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view of the historic development, t
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Table 5. Assumptions for transmutat
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separating troublesome fission prod
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REFERENCES [1] L.H. Baetslé, Ch. D
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SESSION III Partitioning Chairs: J.
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OVERVIEW OF THE HYDROMETALLURGICAL
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2.1.3 Consequences Owing to the fac
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The extraction and separation mecha
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extractant was observed. As a conse
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2.3.2 Examples of strategies and
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3. Conclusions and perspectives 3.1
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SESSION IV Basic Physics, Materials
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TRANSMUTATION: A DECADE OF REVIVAL
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2.1 The IFR concept and the homogen
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2.3 Dedicated systems Making again
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compound “macro-dispersed” in M
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Figure 3. Sketch of ADS, liquid met
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3.3.2.1 The MEGAPIE project [40] ME
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3.3.2.2 The MUSE experiments The MU
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Figure 8. Comparison of the neutron
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Figure 9. Scenarios at equilibrium
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goals in this field. Since once-thr
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• The use of Thorium in PWRs alwa
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• Understanding of the role of AD
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[17] Y. Arai, T. Ogawa, Research on
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SESSION V Transmutation Systems and
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1. Introduction The term ADS compre
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• Safety should be “designed in
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3. Minor actinide and/or transurani
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Table 2. Values of Dj (neutron cons
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Table 4. Delayed neutron fraction I
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Figure 4. η (Neutrons released per
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Table 5. ADS Distinguishing feature
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While a favourable ADS safety featu
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Optimised mixes of MA and Pu can be
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Moreover, the fuel is where neutron
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REFERENCES [1] L. Van den Durpel et
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[19] D.C. Wade and E. Fujita, Trend
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POSTER SESSION Basic Physics: Nucle
- Page 123: To conclude, this poster session in
- Page 126 and 127: Five other papers related to ADS co
- Page 129: SESSION I OVERVIEW OF NATIONAL AND
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- Page 134 and 135: 3.2 Results to date and analyses of
- Page 136 and 137: 3.2.5.2 JNC JNC is considering the
- Page 138 and 139: 4.6 Short-term increase in radiatio
- Page 140 and 141: Annex 1 R&D scheme for partitioning
- Page 142 and 143: Annex 3 Members of the Advisory Com
- Page 144 and 145: plutonium can be recycled in pressu
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- Page 148 and 149: 1. Introduction Since the 5th Infor
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- Page 153 and 154: IAEA ACTIVITIES IN THE AREA OF EMER
- Page 155 and 156: actually started to do so) because
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- Page 163 and 164: current, advanced and innovative nu
- Page 165 and 166: ACCELERATOR DRIVEN SUB-CRITICAL SYS
- Page 167 and 168: demonstration of feasibility of a E
- Page 169 and 170: An extended “skeleton” for ADS
- Page 171 and 172: • Fertile support (uranium) is no
- Page 173: 7. Conclusions The TWG under the ch
- Page 177 and 178: that would be more economical, safe
- Page 179 and 180: compounds will be studied together
- Page 181 and 182: Table 3. Cluster on transmutation-b
- Page 183 and 184: In view of the future research prog
- Page 185 and 186: ACTIVITIES OF OECD/NEA IN THE FRAME
- Page 187 and 188: 2. The previous 10 years The activi
- Page 189 and 190: 4. Scientific issues of P&T In para
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- Page 193 and 194: • Demonstration Experimental Prog
- Page 195: SESSION II THE NUCLEAR FUEL CYCLE A
- Page 198 and 199: 1. Introduction The double-strata f
- Page 200 and 201: Figure 2. Flow-sheet of 4-group par
- Page 202 and 203: from an UO 2 -LWR. The number of tr
- Page 204 and 205: Figure 4. Scenario for development
- Page 207 and 208: TRANSURANICS TRANSMUTATION ON FERTI
- Page 209 and 210: eserved for control bars, shutdown
- Page 211 and 212: Figure 2. Fuel cycle assumed in the
- Page 213 and 214: Reprocessing losses both from the L
- Page 215 and 216: Figure 7: Evolution of k eff of an
- Page 217 and 218: allow to operate for more than 1 20
- Page 219 and 220: ACTINIDE AND FISSION PRODUCT BURNIN
- Page 221 and 222: volume fractions in a wide range co
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The dependencies presented allow ma
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Table 3. Different isotope contribu
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Thus, the introduction of an absorb
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Table 9. 107 Pd transmutation effic
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Table 12. 135 Cs transmutation effi
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REFERENCES [1] M. Salvatores, I. Sl
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1. Introduction Under the provision
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PWR MIX (MOX with enriched uranium)
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Figure 2. Reduction of potential ra
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REFERENCES [1] Stratégie et progra
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1. Introduction Repository design a
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− − − Waste volume. The quant
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underground in salt domes. The HHRs
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quantity of waste, radionuclide rel
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[7] J.J. Cohen, A.E. Lewis and R.L.
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1. Introduction On 30 December 1991
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Once heated, the salt is entrained
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The salt processing unit includes t
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The volume of salt in the fertile a
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Figure 5. Core mass balance for 0.5
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• As we saw earlier, it offers
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SESSION III PARTITIONING SUB-SESSIO
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1. Introduction There is no doubt t
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to be much more ionic than is the c
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Figure 3. One method of the synthes
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REFERENCES [1] Gabriel Y.S. Chan, M
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1. Introduction Radioactive by-prod
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Figure 3. Flowsheet for the hot exp
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Figure 6. Aqueous profiles of fissi
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REFERENCES [1] Z. Kolarik, U. Müll
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1. Introduction Nuclear waste repro
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Figure 3 Cs 2.2 Possibilities of mo
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protonation of [3,3’-Co(1,2-C 2 B
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Figure 8 F O PPh 2 F F F [3] - 6.1
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emarkable the Sr affinity of the fl
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SESSION III PARTITIONING SUB-SESSIO
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1. Introduction The present concept
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transuranics will be reduced to the
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REFERENCE [1] A Roadmap for Develop
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1. Introduction Nuclear waste, espe
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Figure 1. Experimental flame fluori
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5. Laboratory research on electrose
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DEMONSTRATION OF PYROMETALLURGICAL
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Figure 1. Experimental test plan of
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Figure 3. Electrorefiner installed
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Figure 6. Recovered Cd-Pu ingot and
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The separation factor (SF(M)) of me
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[9] T. Inoue, M. Kurata, L. Koch, J
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1. Introduction Metallic fuel cycle
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The electrorefining apparatus and t
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3.1 Time course of LCC potential an
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3.2 Plutonium concentration depende
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crystallized phase in high density.
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Figure 10. Concept of Pu activity c
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REFERENCES [1] Y.I. Chang, The Inte
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SESSION IV BASIC PHYSICS, MATERIALS
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NUCLEAR DATA MEASUREMENTS FOR P&T A
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order to determine σ 0 and I 0 , a
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3.2 Prompt γ-ray spectroscopy For
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REFERENCES [1] H. Harada, H. Watana
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NEW DATA AND MONTE CARLO SIMULATION
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2. General considerations on spalla
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Figure 3. Average neutron multiplic
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4.1 Measurement of residue producti
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Figure 7. Isotopic production cross
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formalism while fission can be desc
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THE MUSE EXPERIMENTS FOR SUB-CRITIC
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The experimental programmes allow t
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The GENEPI accelerator is mainly co
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also experimentally determined usin
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REFERENCES [1] M. Salvatores, M. Ma
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Figure 3. XY loading (at the core m
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OECD/NEA BENCHMARK CALCULATIONS FOR
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The choice of adopting the ALMR ref
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2.1 One-group microscopic cross-sec
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2.2 k eff at beginning of life and
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The burn-up reactivity drop values,
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Figure 7. Axial flux distribution i
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composition at the end of irradiati
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REFERENCES [1] OECD/NEA NSC Task Fo
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STAINLESS STEEL CORROSION IN LEAD-B
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Table 1. Specimens were inserted an
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thermocouples placed in the hot zon
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Figure 6. Auger depth profile conce
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chromium concentration values are l
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For high oxygen activity, alloys wi
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6. Conclusions The results obtained
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ACCUMULATION OF ACTIVATION PRODUCTS
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An important radionuclide determini
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Nuclide Table 4. Nuclide concentrat
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THERMAL AND STRESS ANALYSIS OF HYPE
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The target Pb-Bi is coming from the
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Figure 4. Temperature and velocity
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Figure 6. Target geometry for 3-D c
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Various fuel cycle
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quantities of lanthanide/actinide a
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Figure 4. Densification of MgAl 2 O
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REFERENCES [1] R.J.M. Konings and J
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1. Introduction It is a hard challe
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When recycling Pu but not the minor
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A priori, actinide targets could be
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The deliberate insertion of Am in t
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REFERENCES [1] Th. Maldague et al.,
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1. Introduction The partitioning an
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1 723, 1 823 and 1 923 K in N 2 , N
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A contrast result was also found fo
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Cathodic current was also observed
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On the other hand, the following eq
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REFERENCES [1] Y. Suzuki, T. Ogawa,
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TRANSMUTATION STUDIES IN FRANCE, R&
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concepts for plutonium consumption
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Table 2. Objectives for transmutati
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eing adjusted to take into account
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6.2.1.4 ZrO 2 Due to its low heat c
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Figure 3a. 3D idealised meshing of
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of 5% [24]. The target irradiation
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for the Cochix irradiation (optimis
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• Their high minor actinides (Np,
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REFERENCES [1] P. Bernard, B. Barr
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FISSION PRODUCT TARGET DESIGN FOR H
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2. General description of the core
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3. Basic characteristics of FP tran
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Figure 6. FP target configuration a
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Figure 7. Neutron energy spectrum f
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SAFETY ANALYSIS OF NITRIDE FUELS IN
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worth was calculated by removing al
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component increases with pin pitch,
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4. Conclusions Having calculated th
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ASPECTS OF SEVERE ACCIDENTS IN TRAN
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direct cycle gas-cooled fast spectr
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If an inlet blockage occurred in an
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Another innovative approach is part
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REFERENCES [1] US DOE, Generation I
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A SIMPLE MODEL TO EVALUATE THE NATU
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That in steady state conditions bec
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Moreover, the a leg of the assumed
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2.4 The gravitational pull calculat
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Figure 2. The natural convection im
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REFERENCES [1] C. Rubbia et al., Co
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COMPARATIVE STUDY FOR MINOR ACTINID
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nitride fuel, reflection effect of
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Table 3. Core design parameters for
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2.4 Comparison of neutron spectra T
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The vertical and horizontal axes re
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and adjoint flux. Relatively large
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STUDY ON A LEAD-BISMUTH COOLED ACCE
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Proton beam-trip analysis: In an AD
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Figure 2. Temperature change in pri
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4. Lead-bismuth technology Lead-bis
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Figure 4. Schematic cross-section o
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TRANSURANICS ELIMINATION IN AN OPTI
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Figure 2. Main actinides radiotoxic
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Table 1. Fuel composition Isotope D
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Table 3. Average microscopic cross-
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Table 4. Residual fractions of the
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number of C nuclei is near 2 400 ti
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[12] Salvatores M., Spiro M., The I
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1. Introduction Accelerator driven
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• The sub-critical nuclear core,
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Figure 3. TRU elimination vs. irrad
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Table 4. General characteristics of
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[9] Rugama Y., Muñoz-Cobo J.L., Va
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1. Introduction SCK•CEN, the Belg
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to 40 to 70 MeV and a booster furth
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2.4 Confinement building Parallel t
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3.2 Spallation source The choice of
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• Ente per le Nuove tecnologie, l
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ADS: STATUS OF THE STUDIES PERFORME
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There is no specific need at the fi
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3.4 The primary coolant and the rea
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these fluids and the insurance of n
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• A solid fuel for the transmutat
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its extended use will not become a
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Figure 2. Experimental accelerator
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1. Introduction Nuclear waste can b
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Figure 1. Impact of removing & tran
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epository due to corrosion of the c
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Figure 4. Burn-up of plutonium usin
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accelerator-driven sub-critical mod
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characteristics of this direct (Bra
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The plutonium and minor actinides a
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investigated. Most of the fuel in t
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POSTER SESSIONS 611
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STUDIES ON BEHAVIOUR OF SELENIUM AN
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2.2 Chemical speciation The oxidati
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Figure 2. Isothermal equilibrium cu
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Table 2. Influence of aqueous acid
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Figure 7. Influence of HNO 3 concen
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SOLUBILIZATION STUDIES OF RARE EART
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2. Experiment details Cyclic voltam
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Figure 2 (b). Comparison between th
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Activity coefficients of MeCl 3 in
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Table 2. Solubility products, pk s
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the interactions Me-substrate and M
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CALIX[6]ARENES FUNCTIONALISED WITH
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These compounds were reacted with a
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ACTINIDE(III)/LANTHANIDE(III) PARTI
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2. Experimental 2.1 Synthesis and c
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Figure 3. Americium(III) extraction
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REFERENCES [1] OECD Nuclear Energy
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1. Introduction Nano- and micropart
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3. Selective removal of histidine-t
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Scheme 6. Formation of the macrocyc
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REFERENCES [1] M.D. Kaminski, and L
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NEW EXTRACTANTS FOR PARTITIONING OF
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of COSAN derivatives allowed for us
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On the other hand, all the above an
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All compounds presented above were
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INFLUENCE OF INTERMEDIATE CHEMICAL
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3. Natural or slightly enriched ura
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enrichment 1%, the burn-up grows 1.
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1. Introduction The final disposal
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Table 3. Calculated and experimenta
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Figure 2. General flow-sheet of Tot
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[10] J. Wang, B. Liu, J. Chen, C. S
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DESIGN AND CHARACTERISTICS OF THE n
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The realisation of the present desi
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In the upper right corner of Figure
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Figure 3. Top view of the area wher
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y neutron reactions. The level reac
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The geometry of the beam dump propo
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REFERENCES [1] S. Abramovich et al.
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1. Introduction At the dawn of XXI
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The K parameter value, function of
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3. Experimental results The detecto
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Figure 7: Experimental (full line)
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Figure 9. ENDF/B-VI and JEF2.2 simu
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5. Conclusion The neutron capture c
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1. Experimental set-up The charged
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Figure 2. Preliminary results of do
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REFERENCES [1] Alford W.P. and Spic
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1. Introduction For many accelerato
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eam dump. We observe that the major
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INTERMEDIATE ENERGY NEUTRON-INDUCED
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2. Up-to-date status of the (n,f) c
- Page 725 and 726:
Figure 2. The 181 Ta(n,f), nat W(n,
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obtained more recently. It is seen
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REFERENCES [1] C. Rubbia, The Energ
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[20] P. Staples, P.W. Lisowski, and
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1. Introduction Nuclear fission of
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3. Results and perspectives On the
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Figure 4. Yields of U isotopes in t
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NEUTRON RADIATIVE CAPTURE CROSS-SEC
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15 µA. At the end of the proton be
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conditions with the minimum thermal
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only assumption of the code is that
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4. Conclusions The values of the ne
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DETERMINATION OF THE NEUTRON FISSIO
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Therefore, the neutron induced fiss
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Figure 2. Singles protons and deute
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Following the procedure proposed by
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1. Introduction The renewal interes
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Figure 3. Schematic view of a teles
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Figure 6. Calibration curves used f
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Figure 9. Proton spectrum before an
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this energy and the deuteron data o
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absolute values of proton spectra.
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1. Introduction The HINDAS project
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calculated. Moreover, the optical p
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Figure 2. The Berlin ball detector
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Finally, a new experimental techniq
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REFERENCES [1] S. Benck, I. Slypen,
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1. Introduction In Korea, an accele
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Figure 1. Configuration of the Pb-B
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3. Numerical results The performanc
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operation), respectively. This is b
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790 Figure 6. Normalised radial pow
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REFERENCES [1] W.S. Part et al., HY
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MA AND LLFP TRANSMUTATION IN MTRs A
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70 MW. The beryllium matrix has 79
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Table 1. Neutronic design parameter
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Table 3. Target-volume-averaged dir
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Only the fission process allows com
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amounts of MAs. In addition, one sh
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[9] E. Malambu, Progress Report on
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1. Introduction In the last years t
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4. Core with zirconium hydride in f
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Figure1. Reference reactor core Fig
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Table 4. Comparison of burn-up para
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8. Power distribution in the refere
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where P r is the reactor power, I p
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REMARKS ON KINETICS PARAMETERS OF A
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2. Sub-critical multiplication The
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Figure 2. Radial flux distribution
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Using such a traditional expression
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NOISE METHOD FOR MONITORING THE SUB
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And the descriptor used in noise an
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Figure 1. Amplitude versus frequenc
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As suggested by Uhrig [6], a method
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observed that the precision of the
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1. Introduction Last years importan
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eaches about 0.5% mole at a tempera
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3.2 Precipitation of oxides Althoug
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potentials that must be maintained
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Based on experimental data received
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COMPARATIVE ASSESSMENT OF THE TRANS
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3.1 Reference configuration As in t
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if they are distributed exactly as
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From the perspective of the whole d
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Figure 5. Radial distribution of th
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Table 10. Transmutation rates (kg/T
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1. Introduction The concept of a hi
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underground, the radiation field ge
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REFERENCES [1] T. Iwamura et al., R
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Figure 2. Layout of deep undergroun
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1. Introduction The problem of the
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The data presented show that the ra
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1. Introduction The problem of the
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Table 3. Decay heat power of actini
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1. Scientific activity on ADS in wo
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4. Possible technical tasks on crea
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ON NECESSITY OF CREATION OF ACCELER
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Table 2. Transmutation of 99 Tc wit
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Another important problem concernin
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1. Introduction During the last yea
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Other original proposal of the indi
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Other original offer about sectiona
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concentration of lead in heavy wate
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[5] Kolesov V.P., Gughovski B.Ya.,
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CONDITIONS OF PLUTONIUM, AMERICIUM
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The further increase after 500 days
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decrease. Total actinide amount muc
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DEMONSTRATION ACCELERATOR DRIVEN CO
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Thus, stable nuclides will be forme
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Table 4. Characteristics of linac w
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1. Introduction Nuclear waste radio
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Figure 1. Lengthwise section view o
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Scenario S0. This is our reference
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Scenario 3 shows that mixing of was
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REFERENCES [1] International GT-MHR
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THE USE OF PB-BI EUTECTIC AS THE CO
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P d T = 6.0E+07, time at reactor fu
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The partial differential equations
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Figure 5. Core and heat exchanger p
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with the STAR-CD results is still t
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ONE WAY TO CREATE PROLIFERATION-PRO
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By supposing that FA manufacturing
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exponentially reduces with rather l
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Thus, 232 U generation by only one
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TRANSMUTATION OF LONG-LIVED NUCLIDE
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In the existing open fuel cycle, in
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then include 31% of Np, 66% of Am a
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Let us discuss the radiation balanc
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Higher requirements for the cleanin
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RW disposal is multibarrier configu
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ALSO AVAILABLE ECONOMIC AND TECHNIC
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