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ASSESSMENT OF NUCLEAR POWER SCENARIOS ALLOWING FOR MATRIX BEHAVIOUR IN RADIOLOGICAL IMPACT MODELLING OF DISPOSAL SCENARIOS Eric Tronche 1 , Hubert Boussier 1 , Jean Pavageau 2 1 Commissariat à l’Énergie Atomique (CEA-Valrhô), DCC/DRRV/SSP BP 17171, 30207 Bagnols-sur-Cèze Cedex, France 2 Commissariat à l’Énergie Atomique (CEA-Cadarache), DRN/DER/SPRC Abstract The innovative scientific contribution of this study is to consider a third type of radiotoxic inventory: the potential radiotoxic inventory after conditioning, i.e. taking into account the containment capacity of the radionuclide conditioning matrices. The matrix fraction subjected to alteration over time determines the potential for radionuclide release, hence the notion of the potential radiotoxic inventory after conditioning. An initial comparison of possible scenarios is proposed by considering orders of magnitude for the radionuclide containment capacity of the disposal matrices and for their mobilisation potential. All the scenarios investigated are normalised to the same annual electric power production so that a legitimate comparison can be established for the ultimate waste forms produced per year of operation. This approach reveals significant differences among the scenarios considered that do not appear when only the raw potential radiotoxic inventory is taken into account. The matrix containment performance has a decisive effect on the final impact of a given scenario or type of scenario. Pu recycling scenarios thus reduce the potential radiotoxicity by roughly a factor of 50 compared with an open cycle; the gain rises to a factor of about 300 for scenarios in which Pu and the minor actinides are recycled. Interestingly, the results obtained by the use of a dedicated containment matrix for the minor actinides in a scenario limited to Pu recycling were comparable to those provided by transmutation of the minor actinides. 237
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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
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To conclude, this poster session in
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Five other papers related to ADS co
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SESSION I OVERVIEW OF NATIONAL AND
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1. Current activities for radioacti
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3.2 Results to date and analyses of
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3.2.5.2 JNC JNC is considering the
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4.6 Short-term increase in radiatio
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Annex 1 R&D scheme for partitioning
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Annex 3 Members of the Advisory Com
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plutonium can be recycled in pressu
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choices and the implementation of m
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1. Introduction Since the 5th Infor
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strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
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actually started to do so) because
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establishment of an international R
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The accelerator driven transmutatio
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substantiate this recommendation, s
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current, advanced and innovative nu
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ACCELERATOR DRIVEN SUB-CRITICAL SYS
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demonstration of feasibility of a E
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An extended “skeleton” for ADS
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• Fertile support (uranium) is no
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7. Conclusions The TWG under the ch
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1. Introduction The priorities for
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In the EURATOM Fourth Framework Pro
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Table 2. Cluster on transmutation-t
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6. Community research for the perio
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REFERENCES [1] “Council Decision
Page 186 and 187: 1. Introduction Back in 1989, the O
Page 188 and 189: would need the continuation of tech
Page 190 and 191: individual isotopes as a function o
Page 192 and 193: Therefore, while there is continuin
Page 194 and 195: [9] OECD/NEA, Overview of Physics A
Page 197 and 198: RECENT TOPICS IN R&D FOR THE OMEGA
Page 199 and 200: Figure 1. Partitioning and transmut
Page 201 and 202: The present 4-GPP necessitates a pr
Page 203 and 204: 5. Concluding remarks In 1999, the
Page 205: REFERENCES [1] T. Mukaiyama, T. Tak
Page 208 and 209: 1. Introduction CIEMAT is actively
Page 210 and 211: adiotoxicity to be managed could al
Page 212 and 213: Figure 3. Mass composition of the d
Page 214 and 215: Figure 6. Fuel cycle assumed in the
Page 216 and 217: the 4 batches scheme, allowing to a
Page 218 and 219: Figure 11. Transmutation efficiency
Page 220 and 221: 1. Introduction Spent fuels of mode
Page 222 and 223: Figure 3. A change in radiotoxicity
Page 224 and 225: These dependencies are shown on Fig
Page 226 and 227: When increasing the moderator fract
Page 228 and 229: Even greater power increases are ob
Page 230 and 231: The effect of a moderator volume fr
Page 232 and 233: Table 11. Different isotopes contri
Page 234 and 235: Thus the transmutation of such FPs
Page 238 and 239: 1. Introduction Under the provision
Page 240 and 241: PWR MIX (MOX with enriched uranium)
Page 242 and 243: Figure 2. Reduction of potential ra
Page 244 and 245: REFERENCES [1] Stratégie et progra
Page 246 and 247: 1. Introduction Repository design a
Page 248 and 249: − − − Waste volume. The quant
Page 250 and 251: underground in salt domes. The HHRs
Page 252 and 253: quantity of waste, radionuclide rel
Page 254 and 255: [7] J.J. Cohen, A.E. Lewis and R.L.
Page 256 and 257: 1. Introduction On 30 December 1991
Page 258 and 259: Once heated, the salt is entrained
Page 260 and 261: The salt processing unit includes t
Page 262 and 263: The volume of salt in the fertile a
Page 264 and 265: Figure 5. Core mass balance for 0.5
Page 266 and 267: • As we saw earlier, it offers
Page 269: SESSION III PARTITIONING SUB-SESSIO
Page 272 and 273: 1. Introduction There is no doubt t
Page 274 and 275: to be much more ionic than is the c
Page 276 and 277: Figure 3. One method of the synthes
Page 278 and 279: REFERENCES [1] Gabriel Y.S. Chan, M
Page 280 and 281: 1. Introduction Radioactive by-prod
Page 282 and 283: Figure 3. Flowsheet for the hot exp
Page 284 and 285: Figure 6. Aqueous profiles of fissi
Page 286 and 287:
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
Page 343:
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
Page 381 and 382:
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
Page 436 and 437:
1. Introduction It is a hard challe
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When recycling Pu but not the minor
Page 440 and 441:
A priori, actinide targets could be
Page 442 and 443:
The deliberate insertion of Am in t
Page 444 and 445:
REFERENCES [1] Th. Maldague et al.,
Page 446 and 447:
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
Page 456 and 457:
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,
Page 477 and 478:
REFERENCES [1] P. Bernard, B. Barr
Page 479 and 480:
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
Page 493 and 494:
worth was calculated by removing al
Page 495 and 496:
component increases with pin pitch,
Page 497 and 498:
4. Conclusions Having calculated th
Page 499 and 500:
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
Page 505 and 506:
Another innovative approach is part
Page 507 and 508:
REFERENCES [1] US DOE, Generation I
Page 509 and 510:
A SIMPLE MODEL TO EVALUATE THE NATU
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That in steady state conditions bec
Page 513 and 514:
Moreover, the a leg of the assumed
Page 515 and 516:
2.4 The gravitational pull calculat
Page 517 and 518:
Figure 2. The natural convection im
Page 519 and 520:
REFERENCES [1] C. Rubbia et al., Co
Page 521 and 522:
COMPARATIVE STUDY FOR MINOR ACTINID
Page 523 and 524:
nitride fuel, reflection effect of
Page 525 and 526:
Table 3. Core design parameters for
Page 527 and 528:
2.4 Comparison of neutron spectra T
Page 529 and 530:
The vertical and horizontal axes re
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and adjoint flux. Relatively large
Page 533 and 534:
STUDY ON A LEAD-BISMUTH COOLED ACCE
Page 535 and 536:
Proton beam-trip analysis: In an AD
Page 537 and 538:
Figure 2. Temperature change in pri
Page 539 and 540:
4. Lead-bismuth technology Lead-bis
Page 541 and 542:
Figure 4. Schematic cross-section o
Page 543 and 544:
TRANSURANICS ELIMINATION IN AN OPTI
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Figure 2. Main actinides radiotoxic
Page 547 and 548:
Table 1. Fuel composition Isotope D
Page 549 and 550:
Table 3. Average microscopic cross-
Page 551 and 552:
Table 4. Residual fractions of the
Page 553 and 554:
number of C nuclei is near 2 400 ti
Page 555:
[12] Salvatores M., Spiro M., The I
Page 558 and 559:
1. Introduction Accelerator driven
Page 560 and 561:
• The sub-critical nuclear core,
Page 562 and 563:
Figure 3. TRU elimination vs. irrad
Page 564 and 565:
Table 4. General characteristics of
Page 566 and 567:
[9] Rugama Y., Muñoz-Cobo J.L., Va
Page 568 and 569:
1. Introduction SCK•CEN, the Belg
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to 40 to 70 MeV and a booster furth
Page 572 and 573:
2.4 Confinement building Parallel t
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3.2 Spallation source The choice of
Page 576 and 577:
• Ente per le Nuove tecnologie, l
Page 579 and 580:
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
Page 615 and 616:
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
Page 633 and 634:
Table 2. Solubility products, pk s
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the interactions Me-substrate and M
Page 637 and 638:
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
Page 645 and 646:
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
Page 656 and 657:
REFERENCES [1] M.D. Kaminski, and L
Page 659 and 660:
NEW EXTRACTANTS FOR PARTITIONING OF
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of COSAN derivatives allowed for us
Page 663 and 664:
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.
Page 674 and 675:
1. Introduction The final disposal
Page 676 and 677:
Table 3. Calculated and experimenta
Page 678 and 679:
Figure 2. General flow-sheet of Tot
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[10] J. Wang, B. Liu, J. Chen, C. S
Page 683 and 684:
DESIGN AND CHARACTERISTICS OF THE n
Page 685 and 686:
The realisation of the present desi
Page 687 and 688:
In the upper right corner of Figure
Page 689 and 690:
Figure 3. Top view of the area wher
Page 691 and 692:
y neutron reactions. The level reac
Page 693 and 694:
The geometry of the beam dump propo
Page 695:
REFERENCES [1] S. Abramovich et al.
Page 698 and 699:
1. Introduction At the dawn of XXI
Page 700 and 701:
The K parameter value, function of
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3. Experimental results The detecto
Page 704 and 705:
Figure 7: Experimental (full line)
Page 706 and 707:
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
Page 714 and 715:
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,
Page 727 and 728:
obtained more recently. It is seen
Page 729 and 730:
REFERENCES [1] C. Rubbia, The Energ
Page 731:
[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
Page 745 and 746:
conditions with the minimum thermal
Page 747 and 748:
only assumption of the code is that
Page 749 and 750:
4. Conclusions The values of the ne
Page 751 and 752:
DETERMINATION OF THE NEUTRON FISSIO
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Therefore, the neutron induced fiss
Page 755 and 756:
Figure 2. Singles protons and deute
Page 757:
Following the procedure proposed by
Page 760 and 761:
1. Introduction The renewal interes
Page 762 and 763:
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
Page 770 and 771:
absolute values of proton spectra.
Page 772 and 773:
1. Introduction The HINDAS project
Page 774 and 775:
calculated. Moreover, the optical p
Page 776 and 777:
Figure 2. The Berlin ball detector
Page 778 and 779:
Finally, a new experimental techniq
Page 780 and 781:
REFERENCES [1] S. Benck, I. Slypen,
Page 782 and 783:
1. Introduction In Korea, an accele
Page 784 and 785:
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
Page 805 and 806:
amounts of MAs. In addition, one sh
Page 807:
[9] E. Malambu, Progress Report on
Page 810 and 811:
1. Introduction In the last years t
Page 812 and 813:
4. Core with zirconium hydride in f
Page 814 and 815:
Figure1. Reference reactor core Fig
Page 816 and 817:
Table 4. Comparison of burn-up para
Page 818 and 819:
8. Power distribution in the refere
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where P r is the reactor power, I p
Page 823 and 824:
REMARKS ON KINETICS PARAMETERS OF A
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2. Sub-critical multiplication The
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Figure 2. Radial flux distribution
Page 829 and 830:
Using such a traditional expression
Page 831 and 832:
NOISE METHOD FOR MONITORING THE SUB
Page 833 and 834:
And the descriptor used in noise an
Page 835 and 836:
Figure 1. Amplitude versus frequenc
Page 837 and 838:
As suggested by Uhrig [6], a method
Page 839:
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
Page 853 and 854:
COMPARATIVE ASSESSMENT OF THE TRANS
Page 855 and 856:
3.1 Reference configuration As in t
Page 857 and 858:
if they are distributed exactly as
Page 859 and 860:
From the perspective of the whole d
Page 861 and 862:
Figure 5. Radial distribution of th
Page 863:
Table 10. Transmutation rates (kg/T
Page 866 and 867:
1. Introduction The concept of a hi
Page 868 and 869:
underground, the radiation field ge
Page 870 and 871:
REFERENCES [1] T. Iwamura et al., R
Page 872 and 873:
Figure 2. Layout of deep undergroun
Page 874 and 875:
1. Introduction The problem of the
Page 876 and 877:
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
Page 891:
Another important problem concernin
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1. Introduction During the last yea
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Other original proposal of the indi
Page 898 and 899:
Other original offer about sectiona
Page 900 and 901:
concentration of lead in heavy wate
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[5] Kolesov V.P., Gughovski B.Ya.,
Page 905 and 906:
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
Page 915:
Table 4. Characteristics of linac w
Page 918 and 919:
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
Page 924 and 925:
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
Page 933 and 934:
The partial differential equations
Page 935 and 936:
Figure 5. Core and heat exchanger p
Page 937 and 938:
with the STAR-CD results is still t
Page 939 and 940:
ONE WAY TO CREATE PROLIFERATION-PRO
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By supposing that FA manufacturing
Page 943 and 944:
exponentially reduces with rather l
Page 945 and 946:
Thus, 232 U generation by only one
Page 947 and 948:
TRANSMUTATION OF LONG-LIVED NUCLIDE
Page 949 and 950:
In the existing open fuel cycle, in
Page 951 and 952:
then include 31% of Np, 66% of Am a
Page 953 and 954:
Let us discuss the radiation balanc
Page 955 and 956:
Higher requirements for the cleanin
Page 957 and 958:
RW disposal is multibarrier configu
Page 960 and 961:
ALSO AVAILABLE ECONOMIC AND TECHNIC
Page 962:
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