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SESSION IV BASIC PHYSICS, MATERIALS AND FUELS SUB-SESSION IV-B: MATERIALS 395
Page 1 and 2:
Nuclear Development ACTINIDE AND FI
Page 3 and 4:
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
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Figure 2. The synthesis of ADTPTZ a
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2.4 Implications for partitioning T
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SEPARATION OF MINOR ACTINIDES FROM
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installed in a hot cell. The feed w
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the concentrations of U, Pu and Np
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Table 2 shows the recovery in the r
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PARTITIONING ANIONIC AGENTS BASED O
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which of these, the Co 3+ , Fe 3+ a
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This dianionic species must be extr
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Figure 6 Ph 2 P acetone PPh 2 H2 O
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Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
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[7] J. Rais and P. Selucky, Nucleon
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PYROCHEMICAL PROCESSING OF IRRADIAT
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The metallic cadmium product of the
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Figure 2. Schematic flow-sheet for
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R&D OF PYROCHEMICAL PARTITIONING IN
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(first of all pumps) for fluoride m
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4. Research on material and equipme
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REFERENCES [1] Uhlir J., Pyrochemic
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1. Introduction The increasing inte
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Figure 2. Stainless steel box with
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Figure 4. U deposit on solid cathod
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Figure 7. Schematic flow of the cou
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actinide elements from spent (metal
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DEVELOPMENT OF PLUTONIUM RECOVERY P
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uranium dendrite and that uranium c
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Table 1. Conditions and results of
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Cathode potential went down to -1.6
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Figure 6. Change of LCC potential i
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Figure 9. Relation between Pu conce
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consideration described in the prec
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[13] Y. Arai, S. Fukushima, K. Shio
Page 345: SESSION IV BASIC PHYSICS, MATERIALS
Page 348 and 349: 1. Introduction The reduction of th
Page 350 and 351: agrees ours within limits of errors
Page 352 and 353: Figure 1. Thermal neutron capture c
Page 354 and 355: [18] A.P. Baerg, R.M. Bartholomew,
Page 356 and 357: 1. Introduction Nowadays it is well
Page 358 and 359: In order to describe the inter-nucl
Page 360 and 361: kind of measurements allow to chara
Page 362 and 363: Figure 6. Two-dimensional cluster p
Page 364 and 365: Figure 8. Excitation functions for
Page 366 and 367: REFERENCES [1] D. Ridikas, thesis,
Page 368 and 369: 1. Introduction Since 1991, the Com
Page 370 and 371: Experimental reactivity control tec
Page 372 and 373: Table 2. Neutron intensities Target
Page 374 and 375: experimental channels (horizontal a
Page 376 and 377: 376
Page 378 and 379: Table 3. Planned experimental progr
Page 380 and 381: 1. Introduction and benchmark speci
Page 382 and 383: neutrons. Since the neutron flux is
Page 384 and 385: Figure 2. Microscopic capture cross
Page 386 and 387: Figure 4. k eff variation in the st
Page 388 and 389: 2.4 Neutron flux distribution One r
Page 390 and 391: etween the highest and the lowest v
Page 392 and 393: The isotope specific β eff values
Page 397 and 398: STAINLESS STEEL CORROSION IN LEAD-B
Page 399 and 400: Table 1. Specimens were inserted an
Page 401 and 402: thermocouples placed in the hot zon
Page 403 and 404: Figure 6. Auger depth profile conce
Page 405 and 406: chromium concentration values are l
Page 407 and 408: For high oxygen activity, alloys wi
Page 409 and 410: 6. Conclusions The results obtained
Page 411 and 412: ACCUMULATION OF ACTIVATION PRODUCTS
Page 413 and 414: An important radionuclide determini
Page 415 and 416: Nuclide Table 4. Nuclide concentrat
Page 417 and 418: THERMAL AND STRESS ANALYSIS OF HYPE
Page 419 and 420: The target Pb-Bi is coming from the
Page 421 and 422: Figure 4. Temperature and velocity
Page 423 and 424: Figure 6. Target geometry for 3-D c
Page 425: SESSION IV BASIC PHYSICS, MATERIALS
Page 428 and 429: 1. Introduction Various fuel cycle
Page 430 and 431: quantities of lanthanide/actinide a
Page 432 and 433: Figure 4. Densification of MgAl 2 O
Page 434 and 435: REFERENCES [1] R.J.M. Konings and J
Page 436 and 437: 1. Introduction It is a hard challe
Page 438 and 439: 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
Page 448 and 449:
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
Page 454 and 455:
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&
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,
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
Page 501 and 502:
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
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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
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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
Page 545 and 546:
Figure 2. Main actinides radiotoxic
Page 547 and 548:
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
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
Page 570 and 571:
to 40 to 70 MeV and a booster furth
Page 572 and 573:
2.4 Confinement building Parallel t
Page 574 and 575:
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
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these fluids and the insurance of n
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• A solid fuel for the transmutat
Page 589 and 590:
its extended use will not become a
Page 591:
Figure 2. Experimental accelerator
Page 594 and 595:
1. Introduction Nuclear waste can b
Page 596 and 597:
Figure 1. Impact of removing & tran
Page 598 and 599:
epository due to corrosion of the c
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Figure 4. Burn-up of plutonium usin
Page 602 and 603:
accelerator-driven sub-critical mod
Page 604 and 605:
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
Page 611:
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
Page 621 and 622:
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
Page 631 and 632:
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
Page 641 and 642:
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
Page 647:
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
Page 667 and 668:
INFLUENCE OF INTERMEDIATE CHEMICAL
Page 669 and 670:
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
Page 848 and 849:
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
Page 894 and 895:
1. Introduction During the last yea
Page 896 and 897:
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
Page 902 and 903:
[5] Kolesov V.P., Gughovski B.Ya.,
Page 905 and 906:
CONDITIONS OF PLUTONIUM, AMERICIUM
Page 907 and 908:
The further increase after 500 days
Page 909 and 910:
decrease. Total actinide amount muc
Page 911 and 912:
DEMONSTRATION ACCELERATOR DRIVEN CO
Page 913 and 914:
Thus, stable nuclides will be forme
Page 915:
Table 4. Characteristics of linac w
Page 918 and 919:
1. Introduction Nuclear waste radio
Page 920 and 921:
Figure 1. Lengthwise section view o
Page 922 and 923:
Scenario S0. This is our reference
Page 924 and 925:
Scenario 3 shows that mixing of was
Page 926 and 927:
REFERENCES [1] International GT-MHR
Page 929 and 930:
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
Page 939 and 940:
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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