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DEVELOPMENT OF PLUTONIUM RECOVERY PROCESS BY MOLTEN SALT ELECTROREFINING WITH LIQUID CADMIUM CATHODE Masatoshi Iizuka, Koich Uozumi, Tadashi Inoue Central Research Institute of Electric Power Industry 2-11-1, Iwado-kita, Komae, Tokyo 201-8511, Japan Takashi Iwai, Osamu Shirai, Yasuo Arai Japan Atomic <strong>Energy</strong> Research Institute Oarai, Higashi-Ibaraki, Ibaraki 311-1394, Japan Abstract The effects of electrochemical conditions on the behaviour of plutonium and adequate conditions for recovery at liquid cadmium cathode (LCC) used in pyrometallugical reprocessing were studied with small, not stirred electrodes. Cathodic current density adequate for plutonium collection at LCC was considered to be controlled by diffusion plutonium ion in molten salt and proportional to its concentration. It was shown that plutonium collected at the LCC beyond saturation formed intermetallic compound PuCd 6 and accumulated at the bottom of the LCC. This behaviour of coexisting americium was reasonably explained by the local equilibrium model between plutonium and americium at the surface of the LCC. The plutonium collection rate in practical electrorefining equipment estimated by extrapolation of experimental results was satisfactorily high in designing practical equipment and process. 327
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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
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1. Introduction Back in 1989, the O
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would need the continuation of tech
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individual isotopes as a function o
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Therefore, while there is continuin
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[9] OECD/NEA, Overview of Physics A
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RECENT TOPICS IN R&D FOR THE OMEGA
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Figure 1. Partitioning and transmut
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The present 4-GPP necessitates a pr
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5. Concluding remarks In 1999, the
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REFERENCES [1] T. Mukaiyama, T. Tak
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1. Introduction CIEMAT is actively
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adiotoxicity to be managed could al
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Figure 3. Mass composition of the d
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Figure 6. Fuel cycle assumed in the
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the 4 batches scheme, allowing to a
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Figure 11. Transmutation efficiency
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1. Introduction Spent fuels of mode
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Figure 3. A change in radiotoxicity
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These dependencies are shown on Fig
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When increasing the moderator fract
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Even greater power increases are ob
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The effect of a moderator volume fr
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Table 11. Different isotopes contri
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Thus the transmutation of such FPs
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ASSESSMENT OF NUCLEAR POWER SCENARI
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elease probabilities. The time dist
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Table 2. Annual heavy nuclide contr
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Figure 3. Reduction of potential ra
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DISPOSAL OF PARTITIONING-TRANSMUTAT
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Figure 2. Decay heat from SNF 2000
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Figure 3. Shorter-lived HHR reposit
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4. Management of low-heat, long-liv
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isotope from other caesium isotopes
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THE AMSTER CONCEPT J. Vergnes 1 , D
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Figure 1. Layout diagram of the mol
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Table 1. Definition of configuratio
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We therefore adopted a partial purg
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conceivable. Thus by increasing the
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6. R&D needed to validate the AMSTE
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SESSION III PARTITIONING J.P. Glatz
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PARTITIONING-SEPARATION OF METAL IO
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The terpyridyl reagent (ligand L 1
Page 275 and 276: Figure 2. The synthesis of ADTPTZ a
Page 277 and 278: 2.4 Implications for partitioning T
Page 279 and 280: SEPARATION OF MINOR ACTINIDES FROM
Page 281 and 282: installed in a hot cell. The feed w
Page 283 and 284: the concentrations of U, Pu and Np
Page 285 and 286: Table 2 shows the recovery in the r
Page 287 and 288: PARTITIONING ANIONIC AGENTS BASED O
Page 289 and 290: which of these, the Co 3+ , Fe 3+ a
Page 291 and 292: This dianionic species must be extr
Page 293 and 294: Figure 6 Ph 2 P acetone PPh 2 H2 O
Page 295 and 296: Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
Page 297: [7] J. Rais and P. Selucky, Nucleon
Page 301 and 302: PYROCHEMICAL PROCESSING OF IRRADIAT
Page 303 and 304: The metallic cadmium product of the
Page 305 and 306: Figure 2. Schematic flow-sheet for
Page 307 and 308: R&D OF PYROCHEMICAL PARTITIONING IN
Page 309 and 310: (first of all pumps) for fluoride m
Page 311 and 312: 4. Research on material and equipme
Page 313: REFERENCES [1] Uhlir J., Pyrochemic
Page 316 and 317: 1. Introduction The increasing inte
Page 318 and 319: Figure 2. Stainless steel box with
Page 320 and 321: Figure 4. U deposit on solid cathod
Page 322 and 323: Figure 7. Schematic flow of the cou
Page 324 and 325: actinide elements from spent (metal
Page 328 and 329: 1. Introduction Metallic fuel cycle
Page 330 and 331: The electrorefining apparatus and t
Page 332 and 333: 3.1 Time course of LCC potential an
Page 334 and 335: 3.2 Plutonium concentration depende
Page 336 and 337: crystallized phase in high density.
Page 338 and 339: Figure 10. Concept of Pu activity c
Page 340 and 341: REFERENCES [1] Y.I. Chang, The Inte
Page 343: SESSION IV BASIC PHYSICS, MATERIALS
Page 347 and 348: NUCLEAR DATA MEASUREMENTS FOR P&T A
Page 349 and 350: order to determine σ 0 and I 0 , a
Page 351 and 352: 3.2 Prompt γ-ray spectroscopy For
Page 353 and 354: REFERENCES [1] H. Harada, H. Watana
Page 355 and 356: NEW DATA AND MONTE CARLO SIMULATION
Page 357 and 358: 2. General considerations on spalla
Page 359 and 360: Figure 3. Average neutron multiplic
Page 361 and 362: 4.1 Measurement of residue producti
Page 363 and 364: Figure 7. Isotopic production cross
Page 365 and 366: formalism while fission can be desc
Page 367 and 368: THE MUSE EXPERIMENTS FOR SUB-CRITIC
Page 369 and 370: The experimental programmes allow t
Page 371 and 372: The GENEPI accelerator is mainly co
Page 373 and 374: also experimentally determined usin
Page 375 and 376: REFERENCES [1] M. Salvatores, M. Ma
Page 377 and 378:
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
Page 436 and 437:
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
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
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REFERENCES [1] Y. Suzuki, T. Ogawa,
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TRANSMUTATION STUDIES IN FRANCE, R&
Page 461 and 462:
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
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
Page 511 and 512:
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
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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
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TRANSURANICS ELIMINATION IN AN OPTI
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Figure 2. Main actinides radiotoxic
Page 547 and 548:
Table 1. Fuel composition Isotope D
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Table 3. Average microscopic cross-
Page 551 and 552:
Table 4. Residual fractions of the
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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
Page 581 and 582:
There is no specific need at the fi
Page 583 and 584:
3.4 The primary coolant and the rea
Page 585 and 586:
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
Page 591:
Figure 2. Experimental accelerator
Page 594 and 595:
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
Page 606 and 607:
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
Page 623 and 624:
Figure 7. Influence of HNO 3 concen
Page 625 and 626:
SOLUBILIZATION STUDIES OF RARE EART
Page 627 and 628:
2. Experiment details Cyclic voltam
Page 629 and 630:
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
Page 635 and 636:
the interactions Me-substrate and M
Page 637 and 638:
CALIX[6]ARENES FUNCTIONALISED WITH
Page 639 and 640:
These compounds were reacted with a
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ACTINIDE(III)/LANTHANIDE(III) PARTI
Page 643 and 644:
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
Page 650 and 651:
1. Introduction Nano- and micropart
Page 652 and 653:
3. Selective removal of histidine-t
Page 654 and 655:
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
Page 661 and 662:
of COSAN derivatives allowed for us
Page 663 and 664:
On the other hand, all the above an
Page 665 and 666:
All compounds presented above were
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INFLUENCE OF INTERMEDIATE CHEMICAL
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3. Natural or slightly enriched ura
Page 671:
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
Page 680 and 681:
[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
Page 702 and 703:
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
Page 708 and 709:
5. Conclusion The neutron capture c
Page 710 and 711:
1. Experimental set-up The charged
Page 712 and 713:
Figure 2. Preliminary results of do
Page 714 and 715:
REFERENCES [1] Alford W.P. and Spic
Page 716 and 717:
1. Introduction For many accelerato
Page 718 and 719:
eam dump. We observe that the major
Page 721 and 722:
INTERMEDIATE ENERGY NEUTRON-INDUCED
Page 723 and 724:
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
Page 734 and 735:
1. Introduction Nuclear fission of
Page 736 and 737:
3. Results and perspectives On the
Page 738 and 739:
Figure 4. Yields of U isotopes in t
Page 741 and 742:
NEUTRON RADIATIVE CAPTURE CROSS-SEC
Page 743 and 744:
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
Page 753 and 754:
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
Page 764 and 765:
Figure 6. Calibration curves used f
Page 766 and 767:
Figure 9. Proton spectrum before an
Page 768 and 769:
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
Page 786 and 787:
3. Numerical results The performanc
Page 788 and 789:
operation), respectively. This is b
Page 790 and 791:
790 Figure 6. Normalised radial pow
Page 792 and 793:
REFERENCES [1] W.S. Part et al., HY
Page 795 and 796:
MA AND LLFP TRANSMUTATION IN MTRs A
Page 797 and 798:
70 MW. The beryllium matrix has 79
Page 799 and 800:
Table 1. Neutronic design parameter
Page 801 and 802:
Table 3. Target-volume-averaged dir
Page 803 and 804:
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
Page 820 and 821:
where P r is the reactor power, I p
Page 823 and 824:
REMARKS ON KINETICS PARAMETERS OF A
Page 825 and 826:
2. Sub-critical multiplication The
Page 827 and 828:
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
Page 842 and 843:
1. Introduction Last years importan
Page 844 and 845:
eaches about 0.5% mole at a tempera
Page 846 and 847:
3.2 Precipitation of oxides Althoug
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potentials that must be maintained
Page 850 and 851:
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
Page 878 and 879:
1. Introduction The problem of the
Page 880 and 881:
Table 3. Decay heat power of actini
Page 882 and 883:
1. Scientific activity on ADS in wo
Page 884 and 885:
4. Possible technical tasks on crea
Page 887 and 888:
ON NECESSITY OF CREATION OF ACCELER
Page 889 and 890:
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
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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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