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RECENT TOPICS IN R&D FOR THE OMEGA PROGRAMME IN JAERI Toshitaka Osugi, Hideki Takano, Takakazu Takizuka, Yasuo Arai, Toru Ogawa, Shoichi Tachimori, Yasuji Morita Japan Atomic <strong>Energy</strong> Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, Zip: 319-1195, Japan Abstract The R&D for partitioning and transmutation (P&T) technology has been carried out in Japan since 1988 under the OMEGA (Options for Making Extra Gains from Actinides and fission products) programme. In this programme JAERI has proposed the double-strata fuel cycle concept as a partitioning and transmutation system for long lived radioactive nuclides. The system consists of three technical areas or processes of the partitioning, nuclear transmutation and fuel processes. This paper summarises the JAERI’s activities on these topics, focusing on the recent technical achievements in each process. 197
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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
Page 146 and 147: choices and the implementation of m
Page 148 and 149: 1. Introduction Since the 5th Infor
Page 150 and 151: strata” approach which would invo
Page 153 and 154: IAEA ACTIVITIES IN THE AREA OF EMER
Page 155 and 156: actually started to do so) because
Page 157 and 158: establishment of an international R
Page 159 and 160: The accelerator driven transmutatio
Page 161 and 162: substantiate this recommendation, s
Page 163 and 164: current, advanced and innovative nu
Page 165 and 166: ACCELERATOR DRIVEN SUB-CRITICAL SYS
Page 167 and 168: demonstration of feasibility of a E
Page 169 and 170: An extended “skeleton” for ADS
Page 171 and 172: • Fertile support (uranium) is no
Page 173: 7. Conclusions The TWG under the ch
Page 176 and 177: 1. Introduction The priorities for
Page 178 and 179: In the EURATOM Fourth Framework Pro
Page 180 and 181: Table 2. Cluster on transmutation-t
Page 182 and 183: 6. Community research for the perio
Page 184 and 185: REFERENCES [1] “Council Decision
Page 186 and 187: 1. Introduction Back in 1989, the O
Page 188 and 189: would need the continuation of tech
Page 190 and 191: individual isotopes as a function o
Page 192 and 193: Therefore, while there is continuin
Page 194 and 195: [9] OECD/NEA, Overview of Physics A
Page 198 and 199: 1. Introduction The double-strata f
Page 200 and 201: Figure 2. Flow-sheet of 4-group par
Page 202 and 203: from an UO 2 -LWR. The number of tr
Page 204 and 205: Figure 4. Scenario for development
Page 207 and 208: TRANSURANICS TRANSMUTATION ON FERTI
Page 209 and 210: eserved for control bars, shutdown
Page 211 and 212: Figure 2. Fuel cycle assumed in the
Page 213 and 214: Reprocessing losses both from the L
Page 215 and 216: Figure 7: Evolution of k eff of an
Page 217 and 218: allow to operate for more than 1 20
Page 219 and 220: ACTINIDE AND FISSION PRODUCT BURNIN
Page 221 and 222: volume fractions in a wide range co
Page 223 and 224: equires irradiation times beyond 10
Page 225 and 226: The dependencies presented allow ma
Page 227 and 228: Table 3. Different isotope contribu
Page 229 and 230: Thus, the introduction of an absorb
Page 231 and 232: Table 9. 107 Pd transmutation effic
Page 233 and 234: Table 12. 135 Cs transmutation effi
Page 235: REFERENCES [1] M. Salvatores, I. Sl
Page 238 and 239: 1. Introduction Under the provision
Page 240 and 241: PWR MIX (MOX with enriched uranium)
Page 242 and 243: Figure 2. Reduction of potential ra
Page 244 and 245: REFERENCES [1] Stratégie et progra
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1. Introduction Repository design a
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− − − Waste volume. The quant
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underground in salt domes. The HHRs
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quantity of waste, radionuclide rel
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[7] J.J. Cohen, A.E. Lewis and R.L.
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1. Introduction On 30 December 1991
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Once heated, the salt is entrained
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The salt processing unit includes t
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The volume of salt in the fertile a
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Figure 5. Core mass balance for 0.5
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• As we saw earlier, it offers
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SESSION III PARTITIONING SUB-SESSIO
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1. Introduction There is no doubt t
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to be much more ionic than is the c
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Figure 3. One method of the synthes
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REFERENCES [1] Gabriel Y.S. Chan, M
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1. Introduction Radioactive by-prod
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Figure 3. Flowsheet for the hot exp
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Figure 6. Aqueous profiles of fissi
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REFERENCES [1] Z. Kolarik, U. Müll
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1. Introduction Nuclear waste repro
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Figure 3 Cs 2.2 Possibilities of mo
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protonation of [3,3’-Co(1,2-C 2 B
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Figure 8 F O PPh 2 F F F [3] - 6.1
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emarkable the Sr affinity of the fl
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SESSION III PARTITIONING SUB-SESSIO
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1. Introduction The present concept
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transuranics will be reduced to the
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REFERENCE [1] A Roadmap for Develop
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1. Introduction Nuclear waste, espe
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Figure 1. Experimental flame fluori
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5. Laboratory research on electrose
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DEMONSTRATION OF PYROMETALLURGICAL
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Figure 1. Experimental test plan of
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Figure 3. Electrorefiner installed
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Figure 6. Recovered Cd-Pu ingot and
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The separation factor (SF(M)) of me
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[9] T. Inoue, M. Kurata, L. Koch, J
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1. Introduction Metallic fuel cycle
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The electrorefining apparatus and t
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3.1 Time course of LCC potential an
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3.2 Plutonium concentration depende
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crystallized phase in high density.
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Figure 10. Concept of Pu activity c
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REFERENCES [1] Y.I. Chang, The Inte
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SESSION IV BASIC PHYSICS, MATERIALS
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NUCLEAR DATA MEASUREMENTS FOR P&T A
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order to determine σ 0 and I 0 , a
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3.2 Prompt γ-ray spectroscopy For
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REFERENCES [1] H. Harada, H. Watana
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NEW DATA AND MONTE CARLO SIMULATION
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2. General considerations on spalla
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Figure 3. Average neutron multiplic
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4.1 Measurement of residue producti
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Figure 7. Isotopic production cross
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formalism while fission can be desc
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THE MUSE EXPERIMENTS FOR SUB-CRITIC
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The experimental programmes allow t
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The GENEPI accelerator is mainly co
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also experimentally determined usin
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
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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.,
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1. Introduction The partitioning an
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1 723, 1 823 and 1 923 K in N 2 , N
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A contrast result was also found fo
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Cathodic current was also observed
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On the other hand, the following eq
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
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direct cycle gas-cooled fast spectr
Page 503 and 504:
If an inlet blockage occurred in an
Page 505 and 506:
Another innovative approach is part
Page 507 and 508:
REFERENCES [1] US DOE, Generation I
Page 509 and 510:
A SIMPLE MODEL TO EVALUATE THE NATU
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That in steady state conditions bec
Page 513 and 514:
Moreover, the a leg of the assumed
Page 515 and 516:
2.4 The gravitational pull calculat
Page 517 and 518:
Figure 2. The natural convection im
Page 519 and 520:
REFERENCES [1] C. Rubbia et al., Co
Page 521 and 522:
COMPARATIVE STUDY FOR MINOR ACTINID
Page 523 and 524:
nitride fuel, reflection effect of
Page 525 and 526:
Table 3. Core design parameters for
Page 527 and 528:
2.4 Comparison of neutron spectra T
Page 529 and 530:
The vertical and horizontal axes re
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
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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
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Figure 2. Main actinides radiotoxic
Page 547 and 548:
Table 1. Fuel composition Isotope D
Page 549 and 550:
Table 3. Average microscopic cross-
Page 551 and 552:
Table 4. Residual fractions of the
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number of C nuclei is near 2 400 ti
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[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
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• Ente per le Nuove tecnologie, l
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ADS: STATUS OF THE STUDIES PERFORME
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There is no specific need at the fi
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3.4 The primary coolant and the rea
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these fluids and the insurance of n
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• A solid fuel for the transmutat
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its extended use will not become a
Page 591:
Figure 2. Experimental accelerator
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1. Introduction Nuclear waste can b
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Figure 1. Impact of removing & tran
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epository due to corrosion of the c
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Figure 4. Burn-up of plutonium usin
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accelerator-driven sub-critical mod
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characteristics of this direct (Bra
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The plutonium and minor actinides a
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investigated. Most of the fuel in t
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POSTER SESSIONS 611
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STUDIES ON BEHAVIOUR OF SELENIUM AN
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2.2 Chemical speciation The oxidati
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Figure 2. Isothermal equilibrium cu
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Table 2. Influence of aqueous acid
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Figure 7. Influence of HNO 3 concen
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SOLUBILIZATION STUDIES OF RARE EART
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2. Experiment details Cyclic voltam
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Figure 2 (b). Comparison between th
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Activity coefficients of MeCl 3 in
Page 633 and 634:
Table 2. Solubility products, pk s
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the interactions Me-substrate and M
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CALIX[6]ARENES FUNCTIONALISED WITH
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
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NEW EXTRACTANTS FOR PARTITIONING OF
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of COSAN derivatives allowed for us
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On the other hand, all the above an
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All compounds presented above were
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INFLUENCE OF INTERMEDIATE CHEMICAL
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3. Natural or slightly enriched ura
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enrichment 1%, the burn-up grows 1.
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
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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.
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1. Introduction At the dawn of XXI
Page 700 and 701:
The K parameter value, function of
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3. Experimental results The detecto
Page 704 and 705:
Figure 7: Experimental (full line)
Page 706 and 707:
Figure 9. ENDF/B-VI and JEF2.2 simu
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,
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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
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
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this energy and the deuteron data o
Page 770 and 771:
absolute values of proton spectra.
Page 772 and 773:
1. Introduction The HINDAS project
Page 774 and 775:
calculated. Moreover, the optical p
Page 776 and 777:
Figure 2. The Berlin ball detector
Page 778 and 779:
Finally, a new experimental techniq
Page 780 and 781:
REFERENCES [1] S. Benck, I. Slypen,
Page 782 and 783:
1. Introduction In Korea, an accele
Page 784 and 785:
Figure 1. Configuration of the Pb-B
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
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MA AND LLFP TRANSMUTATION IN MTRs A
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70 MW. The beryllium matrix has 79
Page 799 and 800:
Table 1. Neutronic design parameter
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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
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eaches about 0.5% mole at a tempera
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3.2 Precipitation of oxides Althoug
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potentials that must be maintained
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Based on experimental data received
Page 853 and 854:
COMPARATIVE ASSESSMENT OF THE TRANS
Page 855 and 856:
3.1 Reference configuration As in t
Page 857 and 858:
if they are distributed exactly as
Page 859 and 860:
From the perspective of the whole d
Page 861 and 862:
Figure 5. Radial distribution of th
Page 863:
Table 10. Transmutation rates (kg/T
Page 866 and 867:
1. Introduction The concept of a hi
Page 868 and 869:
underground, the radiation field ge
Page 870 and 871:
REFERENCES [1] T. Iwamura et al., R
Page 872 and 873:
Figure 2. Layout of deep undergroun
Page 874 and 875:
1. Introduction The problem of the
Page 876 and 877:
The data presented show that the ra
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
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4. Possible technical tasks on crea
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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.,
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
Page 935 and 936:
Figure 5. Core and heat exchanger p
Page 937 and 938:
with the STAR-CD results is still t
Page 939 and 940:
ONE WAY TO CREATE PROLIFERATION-PRO
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By supposing that FA manufacturing
Page 943 and 944:
exponentially reduces with rather l
Page 945 and 946:
Thus, 232 U generation by only one
Page 947 and 948:
TRANSMUTATION OF LONG-LIVED NUCLIDE
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In the existing open fuel cycle, in
Page 951 and 952:
then include 31% of Np, 66% of Am a
Page 953 and 954:
Let us discuss the radiation balanc
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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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OECD PUBLICATIONS, 2 rue André-Pas
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