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RESEARCH AND DEVELOPMENT OF TECHNOLOGIES FOR PARTITIONING AND TRANSMUTATION OF LONG-LIVED NUCLIDES IN JAPAN – STATUS AND EVALUATION – Sanae Aoki Director for Planning, Radioactive Waste Policy Division, Science and Technology <strong>Agency</strong> (STA) 2-2-1, Kasumigaseki, Chiyoda-ku ,Tokyo, 100-8966, Japan E-mail: s3aoki@sta.go.jp 131
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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
Page 79 and 80: 3.3.2.2 The MUSE experiments The MU
Page 81 and 82: Figure 8. Comparison of the neutron
Page 83 and 84: Figure 9. Scenarios at equilibrium
Page 85 and 86: goals in this field. Since once-thr
Page 87 and 88: • The use of Thorium in PWRs alwa
Page 89 and 90: • Understanding of the role of AD
Page 91 and 92: [17] Y. Arai, T. Ogawa, Research on
Page 93: SESSION V Transmutation Systems and
Page 96 and 97: 1. Introduction The term ADS compre
Page 98 and 99: • Safety should be “designed in
Page 100 and 101: 3. Minor actinide and/or transurani
Page 102 and 103: Table 2. Values of Dj (neutron cons
Page 104 and 105: Table 4. Delayed neutron fraction I
Page 106 and 107: Figure 4. η (Neutrons released per
Page 108 and 109: Table 5. ADS Distinguishing feature
Page 110 and 111: While a favourable ADS safety featu
Page 112 and 113: Optimised mixes of MA and Pu can be
Page 114 and 115: Moreover, the fuel is where neutron
Page 116 and 117: REFERENCES [1] L. Van den Durpel et
Page 118 and 119: [19] D.C. Wade and E. Fujita, Trend
Page 121 and 122: POSTER SESSION Basic Physics: Nucle
Page 123: To conclude, this poster session in
Page 126 and 127: Five other papers related to ADS co
Page 129: SESSION I OVERVIEW OF NATIONAL AND
Page 133 and 134: The long-term nuclear programme iss
Page 135 and 136: 3.2.3.2 JNC JNC is developing fuel
Page 137 and 138: 4.2 Effects on geological disposal
Page 139 and 140: design and P&T introduction scenari
Page 141 and 142: Annex 2 JAERI JNC CRIEPI 141 Elemen
Page 143 and 144: FRENCH RESEARCH PROGRAMME TO REDUCE
Page 145 and 146: The procedure involves identifying
Page 147 and 148: THE STATUS OF THE US ACCELERATOR TR
Page 149 and 150: of which runs off or is evaporated
Page 151: REFERENCES [1] A Roadmap for Develo
Page 154 and 155: 1. Introduction In the second half
Page 156 and 157: the IAEA Departments of Nuclear Ene
Page 158 and 159: activities is comparison with the a
Page 160 and 161: 17-19 September 1997. Several major
Page 162 and 163: In spite of the above-mentioned dis
Page 164 and 165: LIST OF IAEA PUBLICATIONS 1. Intern
Page 166 and 167: 1. Background In 1998 the Research
Page 168 and 169: form of minor actinides (MAs). Toda
Page 170 and 171: Figure 2. Time schedule and milesto
Page 172 and 173: The accelerator of the XADS has not
Page 175 and 176: PARTITIONING AND TRANSMUTATION IN T
Page 177 and 178: that would be more economical, safe
Page 179 and 180: compounds will be studied together
Page 181 and 182:
Table 3. Cluster on transmutation-b
Page 183 and 184:
In view of the future research prog
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ACTIVITIES OF OECD/NEA IN THE FRAME
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2. The previous 10 years The activi
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4. Scientific issues of P&T In para
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This Working Party will envelop the
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• Demonstration Experimental Prog
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SESSION II THE NUCLEAR FUEL CYCLE A
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1. Introduction The double-strata f
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Figure 2. Flow-sheet of 4-group par
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from an UO 2 -LWR. The number of tr
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Figure 4. Scenario for development
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TRANSURANICS TRANSMUTATION ON FERTI
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eserved for control bars, shutdown
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Figure 2. Fuel cycle assumed in the
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Reprocessing losses both from the L
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Figure 7: Evolution of k eff of an
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allow to operate for more than 1 20
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ACTINIDE AND FISSION PRODUCT BURNIN
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volume fractions in a wide range co
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equires irradiation times beyond 10
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The dependencies presented allow ma
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Table 3. Different isotope contribu
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Thus, the introduction of an absorb
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Table 9. 107 Pd transmutation effic
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Table 12. 135 Cs transmutation effi
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REFERENCES [1] M. Salvatores, I. Sl
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1. Introduction Under the provision
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PWR MIX (MOX with enriched uranium)
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Figure 2. Reduction of potential ra
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REFERENCES [1] Stratégie et progra
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1. Introduction Repository design a
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− − − Waste volume. The quant
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underground in salt domes. The HHRs
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quantity of waste, radionuclide rel
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[7] J.J. Cohen, A.E. Lewis and R.L.
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1. Introduction On 30 December 1991
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Once heated, the salt is entrained
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The salt processing unit includes t
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The volume of salt in the fertile a
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Figure 5. Core mass balance for 0.5
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• As we saw earlier, it offers
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SESSION III PARTITIONING SUB-SESSIO
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1. Introduction There is no doubt t
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to be much more ionic than is the c
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Figure 3. One method of the synthes
Page 278 and 279:
REFERENCES [1] Gabriel Y.S. Chan, M
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1. Introduction Radioactive by-prod
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Figure 3. Flowsheet for the hot exp
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Figure 6. Aqueous profiles of fissi
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
Page 299:
SESSION III PARTITIONING SUB-SESSIO
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1. Introduction The present concept
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transuranics will be reduced to the
Page 306 and 307:
REFERENCE [1] A Roadmap for Develop
Page 308 and 309:
1. Introduction Nuclear waste, espe
Page 310 and 311:
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
Page 325:
[9] T. Inoue, M. Kurata, L. Koch, J
Page 328 and 329:
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
Page 340 and 341:
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
Page 351 and 352:
3.2 Prompt γ-ray spectroscopy For
Page 353 and 354:
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
Page 373 and 374:
also experimentally determined usin
Page 375 and 376:
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
Page 383 and 384:
2.1 One-group microscopic cross-sec
Page 385 and 386:
2.2 k eff at beginning of life and
Page 387 and 388:
The burn-up reactivity drop values,
Page 389 and 390:
Figure 7. Axial flux distribution i
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composition at the end of irradiati
Page 393:
REFERENCES [1] OECD/NEA NSC Task Fo
Page 397 and 398:
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
Page 407 and 408:
For high oxygen activity, alloys wi
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6. Conclusions The results obtained
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ACCUMULATION OF ACTIVATION PRODUCTS
Page 413 and 414:
An important radionuclide determini
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Nuclide Table 4. Nuclide concentrat
Page 417 and 418:
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
Page 423 and 424:
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
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
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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
Page 452 and 453:
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,
Page 459 and 460:
TRANSMUTATION STUDIES IN FRANCE, R&
Page 461 and 462:
concepts for plutonium consumption
Page 463 and 464:
Table 2. Objectives for transmutati
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eing adjusted to take into account
Page 467 and 468:
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
Page 475 and 476:
• 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
Page 483 and 484:
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
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
Page 531 and 532:
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
Page 545 and 546:
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
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
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There is no specific need at the fi
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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
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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
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
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STUDIES ON BEHAVIOUR OF SELENIUM AN
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2.2 Chemical speciation The oxidati
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Figure 2. Isothermal equilibrium cu
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Table 2. Influence of aqueous acid
Page 623 and 624:
Figure 7. Influence of HNO 3 concen
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SOLUBILIZATION STUDIES OF RARE EART
Page 627 and 628:
2. Experiment details Cyclic voltam
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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
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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
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
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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
Page 671:
enrichment 1%, the burn-up grows 1.
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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
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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
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The K parameter value, function of
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3. Experimental results The detecto
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Figure 7: Experimental (full line)
Page 706 and 707:
Figure 9. ENDF/B-VI and JEF2.2 simu
Page 708 and 709:
5. Conclusion The neutron capture c
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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
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INTERMEDIATE ENERGY NEUTRON-INDUCED
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2. Up-to-date status of the (n,f) c
Page 725 and 726:
Figure 2. The 181 Ta(n,f), nat W(n,
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obtained more recently. It is seen
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
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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
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
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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
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Figure 6. Calibration curves used f
Page 766 and 767:
Figure 9. Proton spectrum before an
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this energy and the deuteron data o
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absolute values of proton spectra.
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
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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
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
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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
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if they are distributed exactly as
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From the perspective of the whole d
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Figure 5. Radial distribution of th
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Table 10. Transmutation rates (kg/T
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
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Figure 2. Layout of deep undergroun
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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
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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
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Other original offer about sectiona
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concentration of lead in heavy wate
Page 902 and 903:
[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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