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CONDITIONS OF PLUTONIUM, AMERICIUM AND CURIUM TRANSMUTATION IN NUCLEAR FACILITIES A.S. Gerasimov, G.V. Kiselev, L.A. Myrtsymova, T.S. Zaritskaya State Scientific Centre of the Russian Federation Institute of Theoretical and Experimental Physics (RF SSC ITEP) 25, B. Cheremushkinskaya, 117259 Moscow, Russian Federation Abstract Weapon-grade plutonium burning and transmutation of the americium and curium isotopes from spent nuclear fuel in reactor or accelerator-driven installations with various neutron fluxes and spectra are analysed. The concentration of the nuclides up to 248 Cm and the radiotoxicity are calculated. The problem of plutonium burning and minor actinides transmutation is that the radiotoxicity is increased in the beginning of irradiation, and only after a period it decreases to the initial value. 905
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Nuclear Development ACTINIDE AND FI
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FOREWORD The objective of the OECD/
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TABLE OF CONTENTS Foreword ........
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EXECUTIVE SUMMARY More than 160 par
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identified. In the fuel area, labor
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17:20-19:05 Session III: Partitioni
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Poster sessions Poster session: Par
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WELCOME ADDRESS Lucila Izquierdo Ge
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WELCOME ADDRESS Michel Hugon Co-ord
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WELCOME ADDRESS Philippe Savelli De
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developments. This will surely beco
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use of FBRs for transmutation toget
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view, i.e. better use of uranium an
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W. Forsberg proposes to reduce the
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1. From the open fuel cycle to the
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Figures 2 and 3 show the radiotoxic
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Denoting the transuranic (TRU) or m
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or, in terms of the fuel burn-up an
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quantities of LWR-MOX and FR-MOX wi
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view of the historic development, t
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Table 5. Assumptions for transmutat
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separating troublesome fission prod
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REFERENCES [1] L.H. Baetslé, Ch. D
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SESSION III Partitioning Chairs: J.
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OVERVIEW OF THE HYDROMETALLURGICAL
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2.1.3 Consequences Owing to the fac
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The extraction and separation mecha
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extractant was observed. As a conse
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2.3.2 Examples of strategies and
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3. Conclusions and perspectives 3.1
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SESSION IV Basic Physics, Materials
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TRANSMUTATION: A DECADE OF REVIVAL
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2.1 The IFR concept and the homogen
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2.3 Dedicated systems Making again
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compound “macro-dispersed” in M
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Figure 3. Sketch of ADS, liquid met
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3.3.2.1 The MEGAPIE project [40] ME
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3.3.2.2 The MUSE experiments The MU
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Figure 8. Comparison of the neutron
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Figure 9. Scenarios at equilibrium
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goals in this field. Since once-thr
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• The use of Thorium in PWRs alwa
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• Understanding of the role of AD
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[17] Y. Arai, T. Ogawa, Research on
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SESSION V Transmutation Systems and
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1. Introduction The term ADS compre
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• Safety should be “designed in
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3. Minor actinide and/or transurani
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Table 2. Values of Dj (neutron cons
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Table 4. Delayed neutron fraction I
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Figure 4. η (Neutrons released per
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Table 5. ADS Distinguishing feature
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While a favourable ADS safety featu
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Optimised mixes of MA and Pu can be
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Moreover, the fuel is where neutron
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REFERENCES [1] L. Van den Durpel et
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[19] D.C. Wade and E. Fujita, Trend
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POSTER SESSION Basic Physics: Nucle
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To conclude, this poster session in
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Five other papers related to ADS co
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SESSION I OVERVIEW OF NATIONAL AND
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1. Current activities for radioacti
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3.2 Results to date and analyses of
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3.2.5.2 JNC JNC is considering the
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4.6 Short-term increase in radiatio
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Annex 1 R&D scheme for partitioning
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Annex 3 Members of the Advisory Com
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plutonium can be recycled in pressu
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choices and the implementation of m
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1. Introduction Since the 5th Infor
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strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
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actually started to do so) because
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establishment of an international R
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The accelerator driven transmutatio
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substantiate this recommendation, s
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current, advanced and innovative nu
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ACCELERATOR DRIVEN SUB-CRITICAL SYS
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demonstration of feasibility of a E
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An extended “skeleton” for ADS
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• Fertile support (uranium) is no
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7. Conclusions The TWG under the ch
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1. Introduction The priorities for
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In the EURATOM Fourth Framework Pro
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Table 2. Cluster on transmutation-t
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6. Community research for the perio
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REFERENCES [1] “Council Decision
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1. Introduction Back in 1989, the O
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would need the continuation of tech
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individual isotopes as a function o
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Therefore, while there is continuin
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[9] OECD/NEA, Overview of Physics A
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RECENT TOPICS IN R&D FOR THE OMEGA
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Figure 1. Partitioning and transmut
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The present 4-GPP necessitates a pr
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5. Concluding remarks In 1999, the
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REFERENCES [1] T. Mukaiyama, T. Tak
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1. Introduction CIEMAT is actively
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adiotoxicity to be managed could al
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Figure 3. Mass composition of the d
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Figure 6. Fuel cycle assumed in the
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the 4 batches scheme, allowing to a
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Figure 11. Transmutation efficiency
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1. Introduction Spent fuels of mode
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Figure 3. A change in radiotoxicity
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These dependencies are shown on Fig
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When increasing the moderator fract
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Even greater power increases are ob
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The effect of a moderator volume fr
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Table 11. Different isotopes contri
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Thus the transmutation of such FPs
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ASSESSMENT OF NUCLEAR POWER SCENARI
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elease probabilities. The time dist
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Table 2. Annual heavy nuclide contr
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Figure 3. Reduction of potential ra
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DISPOSAL OF PARTITIONING-TRANSMUTAT
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Figure 2. Decay heat from SNF 2000
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Figure 3. Shorter-lived HHR reposit
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4. Management of low-heat, long-liv
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isotope from other caesium isotopes
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THE AMSTER CONCEPT J. Vergnes 1 , D
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Figure 1. Layout diagram of the mol
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Table 1. Definition of configuratio
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We therefore adopted a partial purg
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conceivable. Thus by increasing the
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6. R&D needed to validate the AMSTE
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SESSION III PARTITIONING J.P. Glatz
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PARTITIONING-SEPARATION OF METAL IO
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The terpyridyl reagent (ligand L 1
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Figure 2. The synthesis of ADTPTZ a
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2.4 Implications for partitioning T
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SEPARATION OF MINOR ACTINIDES FROM
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installed in a hot cell. The feed w
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the concentrations of U, Pu and Np
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Table 2 shows the recovery in the r
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PARTITIONING ANIONIC AGENTS BASED O
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which of these, the Co 3+ , Fe 3+ a
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This dianionic species must be extr
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Figure 6 Ph 2 P acetone PPh 2 H2 O
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Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
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[7] J. Rais and P. Selucky, Nucleon
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PYROCHEMICAL PROCESSING OF IRRADIAT
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The metallic cadmium product of the
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Figure 2. Schematic flow-sheet for
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R&D OF PYROCHEMICAL PARTITIONING IN
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(first of all pumps) for fluoride m
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4. Research on material and equipme
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REFERENCES [1] Uhlir J., Pyrochemic
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1. Introduction The increasing inte
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Figure 2. Stainless steel box with
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Figure 4. U deposit on solid cathod
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Figure 7. Schematic flow of the cou
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actinide elements from spent (metal
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DEVELOPMENT OF PLUTONIUM RECOVERY P
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uranium dendrite and that uranium c
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Table 1. Conditions and results of
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Cathode potential went down to -1.6
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Figure 6. Change of LCC potential i
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Figure 9. Relation between Pu conce
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consideration described in the prec
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[13] Y. Arai, S. Fukushima, K. Shio
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction The reduction of th
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agrees ours within limits of errors
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Figure 1. Thermal neutron capture c
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[18] A.P. Baerg, R.M. Bartholomew,
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1. Introduction Nowadays it is well
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In order to describe the inter-nucl
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kind of measurements allow to chara
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Figure 6. Two-dimensional cluster p
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Figure 8. Excitation functions for
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REFERENCES [1] D. Ridikas, thesis,
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1. Introduction Since 1991, the Com
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Experimental reactivity control tec
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Table 2. Neutron intensities Target
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experimental channels (horizontal a
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376
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Table 3. Planned experimental progr
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1. Introduction and benchmark speci
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neutrons. Since the neutron flux is
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Figure 2. Microscopic capture cross
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Figure 4. k eff variation in the st
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2.4 Neutron flux distribution One r
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etween the highest and the lowest v
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The isotope specific β eff values
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Due to its excellen
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Figure 2. Tests scheme 0 340 h. 1 0
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Figure 4. Auger depth profile conce
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Figure 8. Auger depth profile conce
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deposited at the cold zone, and the
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inner layer grows inward from the o
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[8] V.M. Fedirko, O.I. Eliseeva, V.
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1. Introduction One of the main par
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3. Tantalum target irradiation The
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At 10-MeV neutron irradiation, radi
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1. Introduction HYPER (HYbrid Power
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this study, we used an orthogonal c
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Figure 5. Temperature distribution
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Figure 7. Thermal stress distributi
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FUEL/TARGET CONCEPTS FOR TRANSMUTAT
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(U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
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Figure 3. Left: Ceramograph of a (Z
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Figure 6. Left: ceramograph of a(Zr
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AMERICIUM TARGETS IN FAST REACTORS
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The reference case for all comparis
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It should be underlined that this c
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Cases Table 3. Heterogeneous recycl
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• A later step could be to add Cm
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RESEARCH ON NITRIDE FUEL AND PYROCH
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temperature for (Cm,Pu)N followed t
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Figure 1. Temperature dependence of
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The difference of two fuel pins exi
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In addition to the voltammetric stu
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2 wt% of Pu at 773 K. For the momen
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[13] M. Akabori, M. Takano, A. Itoh
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1. Introduction For the management
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The scientific feasibility of pluto
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Another option using a basis of sta
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6.2.1 Inert matrices 6.2.1.1 MgAl 2
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eached respectively 38.5% and 70% F
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Figure 4. Experiments for MA transm
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Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
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9.3 Programme for dedicated fuels F
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[14] R.J.M. Konings et al., The EFT
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1. Introduction An accelerator driv
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corresponding Pb-Bi velocity is 1.1
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the fission product target. The rod
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fuel rods are at the TRU assembly t
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SESSION V TRANSMUTATION SYSTEMS AND
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1. Introduction Since the 50s, nitr
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A three dimensional model of a sub-
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Figure 4. Change in k-eigenvalue fo
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[4] Y. Arai et al., Experimental Re
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Nomenclature ADS: ATW: GT-MHR: LOF:
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Regarding switching off the beam, o
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Figure 3. Beam blocking 10 min (200
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Figure 7. A possible scenario for n
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[15] Greenspan E. et al., The Encap
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1. Introduction In the EADF design
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Equation (6) can be improved by con
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where L is obtained by a summation
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Figure 1. The natural convection im
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Figure 4 shows the temperature tren
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[12] P.H. Wakker, Thermal Hydraulic
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1. Introduction Research and develo
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Table 2. Core design parameters for
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2.2 Representation of MA transmutat
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Figure 1(b) shows the cases for the
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It is found that the higher MA tran
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REFERENCES [1] T. Ikegami, H. Hayas
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1. Introduction The management of t
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Table 1. Core performance of MA and
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Figure 3. Nuclear electricity capac
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Table 3. Experimental items at PEF
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REFERENCES [1] Takano H., Akie H.,
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1. Introduction and background The
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neutron source, the reactor can mai
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atoms. For fuel region Rf = 2.5 cm,
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Figure 3. Neutron flux spectra for
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A possible way to maintain the k ef
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higher than 99% of 239 Pu, and high
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TRANSMUTATION OF NUCLEAR WASTES WIT
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Figure 1. PBT conceptual view Table
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very tight holders for fission frag
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5. Cooling system A preliminary des
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spectral densities [10,11] and can
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MYRRHA, A MULTI-PURPOSE ADS FOR R&D
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hexagonal assemblies of 122 mm plat
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to achieve the requested performanc
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3 MYRRHA associated R&D programme F
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collaboration with Forschungszentru
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• Industrial partners, in particu
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1. Introduction The transmutation o
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Existing accelerators have been des
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suggested to look for an innovative
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Table 1. Main lead-bismuth eutectic
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4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
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HELIUM-COOLED REACTOR TECHNOLOGIES
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of its potential use in nuclear wea
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Figure 2. Neutron flux distribution
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atio. Given this rate of destructio
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Figure 5. Irradiated TRISO particle
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in ceramic-coated microspheres of t
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(LOCA) event. The effect on this fe
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Figure 13. Elevation AD-FMHR The fa
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Deep burn-up of 239 Pu and fissiona
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POSTER SESSION PARTITIONING M.J. Hu
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1. Introduction The study of the be
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Plutonium was simulated with the no
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The influence of uranium and pluton
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The influence of uranium and pluton
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REFERENCES [1] I.I. Nazarenko, A.M.
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1. Introduction The long-term radio
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Ce Ce 3+ Cl - Cl 2 The voltammogram
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Figure 3. Chronopotentiograms for t
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Figure 4. Potentiometric titrations
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Experimental solubilization tests w
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[13] H. Flood T. Förland and K. Mo
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1. Introduction The separation of l
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Figure 4. Synthesis of amides 11-15
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1. Introduction Over the recent yea
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2.3.2 Set-up We set up a single HFM
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lower flow rates, Am(III) would be
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THE POTENTIAL OF NANO- AND MICROPAR
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efficiently and stable. This can be
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Figure 1a. Zetapotential of NTA-mod
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Scheme 7. Magnetic silica particles
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[13] L.H. Delmau, N. Simon, M.J. Sc
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1. Introduction 137 90 Extraction p
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Figure 3. Schematic drawing of the
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(24), 8-PhPO(OH)-O-COSAN (25), and
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REFERENCES [1] Kyrš M., +H PiQHN S
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1. Introduction A heavy-water CANDU
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These data show that fuel lifetime
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RECENT PROGRESSES ON PARTITIONING S
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hot tests (See Table2) was enough f
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trace amount of Am and Eu. The HBTM
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6. Conclusion Declassification of t
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POSTER SESSION BASIC PHYSICS: NUCLE
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1. Introduction Among the large num
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The simulation of the spallation pr
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Table 1. Parameters of the two coll
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Figure 4. Radial distribution of th
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6. The neutron escape line The comm
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Figure 7. Neutron background at the
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RECENT CAPTURE CROSS-SECTIONS VALID
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Figure 1. The GENEPI accelerator an
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2.3.3 Neutron flux measurements •
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Figure 6. Time spectrum of 3 He gas
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4. Analysis 4.1 Background subtract
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Figure 11. ENDF/B-VI, JEF2.2 and JE
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DOUBLE DIFFERENTIAL CROSS-SECTION F
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3. Conclusion Double differential c
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Figure 3. Preliminary results of do
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MEASUREMENTS OF PARTICULE EMISSION
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2. Experimental set-up The experime
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4. Results Figure 3 presents neutro
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1. Introduction Intermediate-energy
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Table 1. Relative neutron-induced c
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elow about 70 MeV [24] , where σ n
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Since for sub-actinides Γ f /Γ n
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[10] V.P. Eismont, A.V. Prokofiev,
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NUCLEON-INDUCED FISSION CROSS-SECTI
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Figure 1. Scheme of the new code Z
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Figure 3. Neutron-induced fission c
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REFERENCES [1] J. Raynal, Proceedin
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1. Introduction During the past few
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(same surface and 0.5 mm thickness)
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Figure 2. Dependence of the total a
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Figure 3. Neutron radiative capture
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[8] MCNP, A General Monte Carlo Cod
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1. Introduction New reactors using
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Figure 1. Excited states of 209 Bi
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Figure 3. The fission probability o
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MEASUREMENT OF DOUBLE DIFFERENTIAL
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Figure 1. Global view of the experi
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To get the proton (deuteron) energy
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3.1 Corrections Several corrections
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Figure 11. Active target fraction (
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d 2 σ Figure 14. Proton for n + Pb
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HIGH AND INTERMEDIATE ENERGY NUCLEA
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eactions, since the pre-equilibrium
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calculate the very short-lived radi
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cross-sections; the secondary react
Page 779 and 780:
All possible nuclear reactions will
Page 781 and 782:
A STUDY ON BURNABLE ABSORBER FOR A
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2. Burnable absorber for HYPER 2.1
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Table 2. One-group effective cross-
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of the core, is directly determined
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Figure 4. Required proton beam curr
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Figure 8. 10 B depletion in HYPER-H
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POSTER SESSION TRANSMUTATION SYSTEM
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1. Introduction In the framework of
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Φ >1 MeV = 1.0 10 13 to 1.0 x 10 1
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3. Irradiation targets and irradiat
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e transmuted in BR2 hence remain va
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Table 6. Atom percent concentration
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advantage, with respect to FRs, of
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ENHANCEMENT OF ACTINIDE INCINERATIO
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Here Σ fC , ( E) are the fission a
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pellet and the steel cladding. In o
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Table 3.Neutronics parameters of hy
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Figure 3. Neutron spectra averaged
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containing FA with B 4 C cladding i
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REFERENCES [1] ANSALDO Technical Re
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1. Introduction At present, there a
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target means a change in k and the
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Following the normal procedure for
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Acknowledgements This study has bee
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1. ADS description A conceptual des
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Substitution of (9) into (8), and u
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With the coupling LAHET + MCNP-DSP,
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Figure 3. Comparison for 1 and 5 pu
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MOLTEN SALTS AS POSSIBLE FUEL FLUID
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2. The fuel salt for MSB concept Ma
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and minor actinides must be removed
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4. Container material studies 4.1 F
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management. The major developments
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REFERENCES [1] H.J. MacPherson, Dev
Page 854 and 855: 1. Introduction The Energy Amplifie
Page 856 and 857: Table 1. Main parameters of the EAD
Page 858 and 859: Table 5. Neutron balance in the who
Page 860 and 861: Table 7. Neutron flux distributions
Page 862 and 863: Table 8. Displacement rates DPA/yea
Page 865 and 866: DEEP UNDERGROUND TRANSMUTOR (PASSIV
Page 867 and 868: passive state. By operating at a hi
Page 869 and 870: I have proposed using an accelerato
Page 871 and 872: Figure 1. Layout of deep undergroun
Page 873 and 874: RADIATION CHARACTERISTICS OF PWR MO
Page 875 and 876: Table 1. Radiotoxicity of actinides
Page 877 and 878: RADIATION CHARACTERISTICS OF URANIU
Page 879 and 880: Table 1. Radiotoxicity of actinides
Page 881 and 882: INTERNATIONAL CO-OPERATION ON CREAT
Page 883 and 884: an international base to combine ef
Page 885: • Second topic: interaction of pr
Page 888 and 889: 1. Introduction The role of acceler
Page 890 and 891: MEPI within the framework of Projec
Page 893 and 894: NEW ORIGINAL IDEAS ON ACCELERATOR D
Page 895 and 896: During conceptual investigations of
Page 897 and 898: delay, interface and computer. The
Page 899 and 900: 2. Channel-vessel design of ADS bla
Page 901 and 902: Table 1. Characteristics of the ful
Page 903: [14] Karavaev G.N., Kiselev G.V., M
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
Page 931 and 932: P d T = 6.0E+07, time at reactor fu
Page 933 and 934: 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
Page 941 and 942: 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
Page 949 and 950: 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
Page 957 and 958:
RW disposal is multibarrier configu
Page 960 and 961:
ALSO AVAILABLE ECONOMIC AND TECHNIC
Page 962:
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