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SAFETY CONSIDERATIONS IN DESIGN OF FAST SPECTRUM ADS FOR TRANSURANIC OR MINOR ACTINIDE BURNING: A STATUS REPORT ON ACTIVITIES OF THE OECD/NEA EXPERT GROUP OVERVIEW PAPER D.C. Wade Argonne National Laboratory 9700 S. Cass Avenue, Building 208, Argonne, IL 60439, USA Abstract The Nuclear Development Committee of the OECD/NEA convened an expert group for a “Comparative Study of Accelerator Driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles”. The expert group has studied complexes (i.e. energy parks) of fission-based energy production and associated waste management facilities comprised of thermal and fast reactors, and ADS. With a goal to minimise transuranic (TRU) flows to the repository per unit of useful energy provided by the complex, the expert group has studied homogenous and heterogeneous recycle of TRU and minor actinides (MA) in the facilities of the complex using aqueous or dry recycle in single and double strata architectures. In the complexes considered by the expert group the ADS is always assigned a TRU or MA (and sometimes a LLFP) incineration mission – with useful energy production only as a secondary ADS goal to partially offset the cost of its construction and operation. Ancillary issues have also been considered – including ADS safety challenges and strategies for resolving them. This paper reports on the status of the expert group’s considerations of ADS safety strategy. 95
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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
Page 44 and 45: Table 5. Assumptions for transmutat
Page 46 and 47: separating troublesome fission prod
Page 48 and 49: REFERENCES [1] L.H. Baetslé, Ch. D
Page 51 and 52: SESSION III Partitioning Chairs: J.
Page 53 and 54: OVERVIEW OF THE HYDROMETALLURGICAL
Page 55 and 56: 2.1.3 Consequences Owing to the fac
Page 57 and 58: The extraction and separation mecha
Page 59 and 60: extractant was observed. As a conse
Page 61 and 62: 2.3.2 Examples of strategies and
Page 63 and 64: 3. Conclusions and perspectives 3.1
Page 65 and 66: SESSION IV Basic Physics, Materials
Page 67 and 68: TRANSMUTATION: A DECADE OF REVIVAL
Page 69 and 70: 2.1 The IFR concept and the homogen
Page 71 and 72: 2.3 Dedicated systems Making again
Page 73 and 74: compound “macro-dispersed” in M
Page 75 and 76: Figure 3. Sketch of ADS, liquid met
Page 77 and 78: 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 97 and 98: The approach taken by the expert gr
Page 99 and 100: 2.2 Safety strategies Strategies to
Page 101 and 102: composition; this composition depen
Page 103 and 104: Table 3. Radiotoxicity data (CD = C
Page 105 and 106: to vary from loading to loading as
Page 107 and 108: the desired heat rating and on the
Page 109 and 110: Proton beam transport tube and spal
Page 111 and 112: Freezing temperatures and coolant/s
Page 113 and 114: The prompt neutron population estab
Page 115 and 116: feedbacks successfully exploited an
Page 117 and 118: [10] a) R.A. Wigeland, Comparison o
Page 119: POSTER SESSION Partitioning Chair:
Page 122 and 123: The fourth paper reported on measur
Page 125 and 126: POSTER SESSION Transmutation System
Page 127: CD-ROM CONTENTS AND INSTRUCTIONS FO
Page 131 and 132: RESEARCH AND DEVELOPMENT OF TECHNOL
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
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The procedure involves identifying
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THE STATUS OF THE US ACCELERATOR TR
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of which runs off or is evaporated
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REFERENCES [1] A Roadmap for Develo
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1. Introduction In the second half
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the IAEA Departments of Nuclear Ene
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activities is comparison with the a
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17-19 September 1997. Several major
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In spite of the above-mentioned dis
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LIST OF IAEA PUBLICATIONS 1. Intern
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1. Background In 1998 the Research
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form of minor actinides (MAs). Toda
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Figure 2. Time schedule and milesto
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The accelerator of the XADS has not
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PARTITIONING AND TRANSMUTATION IN T
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that would be more economical, safe
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compounds will be studied together
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Table 3. Cluster on transmutation-b
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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
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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
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REFERENCES [1] M. Salvatores, M. Ma
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Figure 3. XY loading (at the core m
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OECD/NEA BENCHMARK CALCULATIONS FOR
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The choice of adopting the ALMR ref
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2.1 One-group microscopic cross-sec
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2.2 k eff at beginning of life and
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The burn-up reactivity drop values,
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Figure 7. Axial flux distribution i
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composition at the end of irradiati
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REFERENCES [1] OECD/NEA NSC Task Fo
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STAINLESS STEEL CORROSION IN LEAD-B
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Table 1. Specimens were inserted an
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thermocouples placed in the hot zon
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Figure 6. Auger depth profile conce
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chromium concentration values are l
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For high oxygen activity, alloys wi
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6. Conclusions The results obtained
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ACCUMULATION OF ACTIVATION PRODUCTS
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An important radionuclide determini
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Nuclide Table 4. Nuclide concentrat
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THERMAL AND STRESS ANALYSIS OF HYPE
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The target Pb-Bi is coming from the
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Figure 4. Temperature and velocity
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Figure 6. Target geometry for 3-D c
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Various fuel cycle
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quantities of lanthanide/actinide a
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Figure 4. Densification of MgAl 2 O
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REFERENCES [1] R.J.M. Konings and J
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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
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The deliberate insertion of Am in t
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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
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REFERENCES [1] Y. Suzuki, T. Ogawa,
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TRANSMUTATION STUDIES IN FRANCE, R&
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concepts for plutonium consumption
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Table 2. Objectives for transmutati
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eing adjusted to take into account
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6.2.1.4 ZrO 2 Due to its low heat c
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Figure 3a. 3D idealised meshing of
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of 5% [24]. The target irradiation
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for the Cochix irradiation (optimis
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• Their high minor actinides (Np,
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REFERENCES [1] P. Bernard, B. Barr
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FISSION PRODUCT TARGET DESIGN FOR H
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2. General description of the core
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3. Basic characteristics of FP tran
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Figure 6. FP target configuration a
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Figure 7. Neutron energy spectrum f
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SAFETY ANALYSIS OF NITRIDE FUELS IN
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worth was calculated by removing al
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component increases with pin pitch,
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4. Conclusions Having calculated th
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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
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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
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2.4 The gravitational pull calculat
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Figure 2. The natural convection im
Page 519 and 520:
REFERENCES [1] C. Rubbia et al., Co
Page 521 and 522:
COMPARATIVE STUDY FOR MINOR ACTINID
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nitride fuel, reflection effect of
Page 525 and 526:
Table 3. Core design parameters for
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2.4 Comparison of neutron spectra T
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The vertical and horizontal axes re
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and adjoint flux. Relatively large
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STUDY ON A LEAD-BISMUTH COOLED ACCE
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Proton beam-trip analysis: In an AD
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Figure 2. Temperature change in pri
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4. Lead-bismuth technology Lead-bis
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Figure 4. Schematic cross-section o
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TRANSURANICS ELIMINATION IN AN OPTI
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Figure 2. Main actinides radiotoxic
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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
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[12] Salvatores M., Spiro M., The I
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1. Introduction Accelerator driven
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• The sub-critical nuclear core,
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Figure 3. TRU elimination vs. irrad
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Table 4. General characteristics of
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[9] Rugama Y., Muñoz-Cobo J.L., Va
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1. Introduction SCK•CEN, the Belg
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to 40 to 70 MeV and a booster furth
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2.4 Confinement building Parallel t
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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
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Figure 2. Experimental accelerator
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1. Introduction Nuclear waste can b
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Figure 1. Impact of removing & tran
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epository due to corrosion of the c
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Figure 4. Burn-up of plutonium usin
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accelerator-driven sub-critical mod
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characteristics of this direct (Bra
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The plutonium and minor actinides a
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investigated. Most of the fuel in t
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POSTER SESSIONS 611
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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
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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
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These compounds were reacted with a
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ACTINIDE(III)/LANTHANIDE(III) PARTI
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2. Experimental 2.1 Synthesis and c
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Figure 3. Americium(III) extraction
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REFERENCES [1] OECD Nuclear Energy
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1. Introduction Nano- and micropart
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3. Selective removal of histidine-t
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Scheme 6. Formation of the macrocyc
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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.
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1. Introduction The final disposal
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Table 3. Calculated and experimenta
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Figure 2. General flow-sheet of Tot
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[10] J. Wang, B. Liu, J. Chen, C. S
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DESIGN AND CHARACTERISTICS OF THE n
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The realisation of the present desi
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In the upper right corner of Figure
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Figure 3. Top view of the area wher
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y neutron reactions. The level reac
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The geometry of the beam dump propo
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REFERENCES [1] S. Abramovich et al.
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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)
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Figure 9. ENDF/B-VI and JEF2.2 simu
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5. Conclusion The neutron capture c
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1. Experimental set-up The charged
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Figure 2. Preliminary results of do
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REFERENCES [1] Alford W.P. and Spic
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1. Introduction For many accelerato
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eam dump. We observe that the major
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INTERMEDIATE ENERGY NEUTRON-INDUCED
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2. Up-to-date status of the (n,f) c
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Figure 2. The 181 Ta(n,f), nat W(n,
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obtained more recently. It is seen
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REFERENCES [1] C. Rubbia, The Energ
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[20] P. Staples, P.W. Lisowski, and
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1. Introduction Nuclear fission of
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3. Results and perspectives On the
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Figure 4. Yields of U isotopes in t
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NEUTRON RADIATIVE CAPTURE CROSS-SEC
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15 µA. At the end of the proton be
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conditions with the minimum thermal
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only assumption of the code is that
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4. Conclusions The values of the ne
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DETERMINATION OF THE NEUTRON FISSIO
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Therefore, the neutron induced fiss
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Figure 2. Singles protons and deute
Page 757:
Following the procedure proposed by
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1. Introduction The renewal interes
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Figure 3. Schematic view of a teles
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Figure 6. Calibration curves used f
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Figure 9. Proton spectrum before an
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this energy and the deuteron data o
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absolute values of proton spectra.
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1. Introduction The HINDAS project
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calculated. Moreover, the optical p
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Figure 2. The Berlin ball detector
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Finally, a new experimental techniq
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REFERENCES [1] S. Benck, I. Slypen,
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1. Introduction In Korea, an accele
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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
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[9] E. Malambu, Progress Report on
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1. Introduction In the last years t
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4. Core with zirconium hydride in f
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Figure1. Reference reactor core Fig
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Table 4. Comparison of burn-up para
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8. Power distribution in the refere
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where P r is the reactor power, I p
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REMARKS ON KINETICS PARAMETERS OF A
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2. Sub-critical multiplication The
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Figure 2. Radial flux distribution
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Using such a traditional expression
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NOISE METHOD FOR MONITORING THE SUB
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And the descriptor used in noise an
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Figure 1. Amplitude versus frequenc
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As suggested by Uhrig [6], a method
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observed that the precision of the
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1. Introduction Last years importan
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eaches about 0.5% mole at a tempera
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3.2 Precipitation of oxides Althoug
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potentials that must be maintained
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Based on experimental data received
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COMPARATIVE ASSESSMENT OF THE TRANS
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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
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1. Introduction The concept of a hi
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underground, the radiation field ge
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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
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The data presented show that the ra
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1. Introduction The problem of the
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Table 3. Decay heat power of actini
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1. Scientific activity on ADS in wo
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4. Possible technical tasks on crea
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ON NECESSITY OF CREATION OF ACCELER
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Table 2. Transmutation of 99 Tc wit
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Another important problem concernin
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1. Introduction During the last yea
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Other original proposal of the indi
Page 898 and 899:
Other original offer about sectiona
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concentration of lead in heavy wate
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[5] Kolesov V.P., Gughovski B.Ya.,
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CONDITIONS OF PLUTONIUM, AMERICIUM
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The further increase after 500 days
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decrease. Total actinide amount muc
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DEMONSTRATION ACCELERATOR DRIVEN CO
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Thus, stable nuclides will be forme
Page 915:
Table 4. Characteristics of linac w
Page 918 and 919:
1. Introduction Nuclear waste radio
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Figure 1. Lengthwise section view o
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Scenario S0. This is our reference
Page 924 and 925:
Scenario 3 shows that mixing of was
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REFERENCES [1] International GT-MHR
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THE USE OF PB-BI EUTECTIC AS THE CO
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P d T = 6.0E+07, time at reactor fu
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The partial differential equations
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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
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exponentially reduces with rather l
Page 945 and 946:
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
Page 951 and 952:
then include 31% of Np, 66% of Am a
Page 953 and 954:
Let us discuss the radiation balanc
Page 955 and 956:
Higher requirements for the cleanin
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RW disposal is multibarrier configu
Page 960 and 961:
ALSO AVAILABLE ECONOMIC AND TECHNIC
Page 962:
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