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NEW EXTRACTANTS FOR PARTITIONING OF FISSION PRODUCTS J. Plešek, B. Grüner, J. %iþD Institute of Inorganic Chemistry, 5Hå, Czech Republic P. Selucký, J. Rais, N.V. Šistková <strong>Nuclear</strong> Research Institute 5Hå, 5Hå, Czech Republic B. ýasenský Katchem, 5Hå, Czech Republic Abstract New progress made in the field of dicarbollide [closo-commo-(1,2-C 2 B 9 H 11 ) 2 -3Co)] - (COSANs) based extractants for partitioning of fission product from spent nuclear fuel, especially Sr 2+ and actinides, made during past years in the Czech Republic, are described in the paper. The synthetic methods for two classes of new extraction agents containing in the molecule either hydrophobic arylene bridge substituents or metal selective groups with donor atoms able to co-ordinate polyvalent cations have been developed. The structures of the recently prepared extraction reagents are presented, along with ideas on which syntheses were based and the basic relations between structures and extraction properties of the compounds. 659
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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
Page 366 and 367:
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
Page 460 and 461:
1. Introduction For the management
Page 462 and 463:
The scientific feasibility of pluto
Page 464 and 465:
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
Page 484 and 485:
the fission product target. The rod
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fuel rods are at the TRU assembly t
Page 489:
SESSION V TRANSMUTATION SYSTEMS AND
Page 492 and 493:
1. Introduction Since the 50s, nitr
Page 494 and 495:
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:
Page 502 and 503:
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
Page 508 and 509:
[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
Page 514 and 515:
where L is obtained by a summation
Page 516 and 517:
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
Page 522 and 523:
1. Introduction Research and develo
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Table 2. Core design parameters for
Page 526 and 527:
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
Page 534 and 535:
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
Page 542 and 543:
REFERENCES [1] Takano H., Akie H.,
Page 544 and 545:
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
Page 561 and 562:
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
Page 567 and 568:
MYRRHA, A MULTI-PURPOSE ADS FOR R&D
Page 569 and 570:
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
Page 582 and 583:
Existing accelerators have been des
Page 584 and 585:
suggested to look for an innovative
Page 586 and 587:
Table 1. Main lead-bismuth eutectic
Page 588 and 589:
4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
Page 593 and 594:
HELIUM-COOLED REACTOR TECHNOLOGIES
Page 595 and 596:
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
Page 607 and 608: Figure 13. Elevation AD-FMHR The fa
Page 609: Deep burn-up of 239 Pu and fissiona
Page 613: POSTER SESSION PARTITIONING M.J. Hu
Page 616 and 617: 1. Introduction The study of the be
Page 618 and 619: Plutonium was simulated with the no
Page 620 and 621: The influence of uranium and pluton
Page 622 and 623: The influence of uranium and pluton
Page 624 and 625: REFERENCES [1] I.I. Nazarenko, A.M.
Page 626 and 627: 1. Introduction The long-term radio
Page 628 and 629: Ce Ce 3+ Cl - Cl 2 The voltammogram
Page 630 and 631: Figure 3. Chronopotentiograms for t
Page 632 and 633: Figure 4. Potentiometric titrations
Page 634 and 635: Experimental solubilization tests w
Page 636 and 637: [13] H. Flood T. Förland and K. Mo
Page 638 and 639: 1. Introduction The separation of l
Page 640 and 641: Figure 4. Synthesis of amides 11-15
Page 642 and 643: 1. Introduction Over the recent yea
Page 644 and 645: 2.3.2 Set-up We set up a single HFM
Page 646 and 647: lower flow rates, Am(III) would be
Page 649 and 650: THE POTENTIAL OF NANO- AND MICROPAR
Page 651 and 652: efficiently and stable. This can be
Page 653 and 654: Figure 1a. Zetapotential of NTA-mod
Page 655 and 656: Scheme 7. Magnetic silica particles
Page 657: [13] L.H. Delmau, N. Simon, M.J. Sc
Page 661 and 662: of COSAN derivatives allowed for us
Page 663 and 664: On the other hand, all the above an
Page 665 and 666: All compounds presented above were
Page 667 and 668: INFLUENCE OF INTERMEDIATE CHEMICAL
Page 669 and 670: 3. Natural or slightly enriched ura
Page 671: enrichment 1%, the burn-up grows 1.
Page 674 and 675: 1. Introduction The final disposal
Page 676 and 677: Table 3. Calculated and experimenta
Page 678 and 679: Figure 2. General flow-sheet of Tot
Page 680 and 681: [10] J. Wang, B. Liu, J. Chen, C. S
Page 683 and 684: DESIGN AND CHARACTERISTICS OF THE n
Page 685 and 686: The realisation of the present desi
Page 687 and 688: In the upper right corner of Figure
Page 689 and 690: Figure 3. Top view of the area wher
Page 691 and 692: y neutron reactions. The level reac
Page 693 and 694: The geometry of the beam dump propo
Page 695: REFERENCES [1] S. Abramovich et al.
Page 698 and 699: 1. Introduction At the dawn of XXI
Page 700 and 701: The K parameter value, function of
Page 702 and 703: 3. Experimental results The detecto
Page 704 and 705: Figure 7: Experimental (full line)
Page 706 and 707: Figure 9. ENDF/B-VI and JEF2.2 simu
Page 708 and 709:
5. Conclusion The neutron capture c
Page 710 and 711:
1. Experimental set-up The charged
Page 712 and 713:
Figure 2. Preliminary results of do
Page 714 and 715:
REFERENCES [1] Alford W.P. and Spic
Page 716 and 717:
1. Introduction For many accelerato
Page 718 and 719:
eam dump. We observe that the major
Page 721 and 722:
INTERMEDIATE ENERGY NEUTRON-INDUCED
Page 723 and 724:
2. Up-to-date status of the (n,f) c
Page 725 and 726:
Figure 2. The 181 Ta(n,f), nat W(n,
Page 727 and 728:
obtained more recently. It is seen
Page 729 and 730:
REFERENCES [1] C. Rubbia, The Energ
Page 731:
[20] P. Staples, P.W. Lisowski, and
Page 734 and 735:
1. Introduction Nuclear fission of
Page 736 and 737:
3. Results and perspectives On the
Page 738 and 739:
Figure 4. Yields of U isotopes in t
Page 741 and 742:
NEUTRON RADIATIVE CAPTURE CROSS-SEC
Page 743 and 744:
15 µA. At the end of the proton be
Page 745 and 746:
conditions with the minimum thermal
Page 747 and 748:
only assumption of the code is that
Page 749 and 750:
4. Conclusions The values of the ne
Page 751 and 752:
DETERMINATION OF THE NEUTRON FISSIO
Page 753 and 754:
Therefore, the neutron induced fiss
Page 755 and 756:
Figure 2. Singles protons and deute
Page 757:
Following the procedure proposed by
Page 760 and 761:
1. Introduction The renewal interes
Page 762 and 763:
Figure 3. Schematic view of a teles
Page 764 and 765:
Figure 6. Calibration curves used f
Page 766 and 767:
Figure 9. Proton spectrum before an
Page 768 and 769:
this energy and the deuteron data o
Page 770 and 771:
absolute values of proton spectra.
Page 772 and 773:
1. Introduction The HINDAS project
Page 774 and 775:
calculated. Moreover, the optical p
Page 776 and 777:
Figure 2. The Berlin ball detector
Page 778 and 779:
Finally, a new experimental techniq
Page 780 and 781:
REFERENCES [1] S. Benck, I. Slypen,
Page 782 and 783:
1. Introduction In Korea, an accele
Page 784 and 785:
Figure 1. Configuration of the Pb-B
Page 786 and 787:
3. Numerical results The performanc
Page 788 and 789:
operation), respectively. This is b
Page 790 and 791:
790 Figure 6. Normalised radial pow
Page 792 and 793:
REFERENCES [1] W.S. Part et al., HY
Page 795 and 796:
MA AND LLFP TRANSMUTATION IN MTRs A
Page 797 and 798:
70 MW. The beryllium matrix has 79
Page 799 and 800:
Table 1. Neutronic design parameter
Page 801 and 802:
Table 3. Target-volume-averaged dir
Page 803 and 804:
Only the fission process allows com
Page 805 and 806:
amounts of MAs. In addition, one sh
Page 807:
[9] E. Malambu, Progress Report on
Page 810 and 811:
1. Introduction In the last years t
Page 812 and 813:
4. Core with zirconium hydride in f
Page 814 and 815:
Figure1. Reference reactor core Fig
Page 816 and 817:
Table 4. Comparison of burn-up para
Page 818 and 819:
8. Power distribution in the refere
Page 820 and 821:
where P r is the reactor power, I p
Page 823 and 824:
REMARKS ON KINETICS PARAMETERS OF A
Page 825 and 826:
2. Sub-critical multiplication The
Page 827 and 828:
Figure 2. Radial flux distribution
Page 829 and 830:
Using such a traditional expression
Page 831 and 832:
NOISE METHOD FOR MONITORING THE SUB
Page 833 and 834:
And the descriptor used in noise an
Page 835 and 836:
Figure 1. Amplitude versus frequenc
Page 837 and 838:
As suggested by Uhrig [6], a method
Page 839:
observed that the precision of the
Page 842 and 843:
1. Introduction Last years importan
Page 844 and 845:
eaches about 0.5% mole at a tempera
Page 846 and 847:
3.2 Precipitation of oxides Althoug
Page 848 and 849:
potentials that must be maintained
Page 850 and 851:
Based on experimental data received
Page 853 and 854:
COMPARATIVE ASSESSMENT OF THE TRANS
Page 855 and 856:
3.1 Reference configuration As in t
Page 857 and 858:
if they are distributed exactly as
Page 859 and 860:
From the perspective of the whole d
Page 861 and 862:
Figure 5. Radial distribution of th
Page 863:
Table 10. Transmutation rates (kg/T
Page 866 and 867:
1. Introduction The concept of a hi
Page 868 and 869:
underground, the radiation field ge
Page 870 and 871:
REFERENCES [1] T. Iwamura et al., R
Page 872 and 873:
Figure 2. Layout of deep undergroun
Page 874 and 875:
1. Introduction The problem of the
Page 876 and 877:
The data presented show that the ra
Page 878 and 879:
1. Introduction The problem of the
Page 880 and 881:
Table 3. Decay heat power of actini
Page 882 and 883:
1. Scientific activity on ADS in wo
Page 884 and 885:
4. Possible technical tasks on crea
Page 887 and 888:
ON NECESSITY OF CREATION OF ACCELER
Page 889 and 890:
Table 2. Transmutation of 99 Tc wit
Page 891:
Another important problem concernin
Page 894 and 895:
1. Introduction During the last yea
Page 896 and 897:
Other original proposal of the indi
Page 898 and 899:
Other original offer about sectiona
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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
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1. Introduction Nuclear waste radio
Page 920 and 921:
Figure 1. Lengthwise section view o
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Scenario S0. This is our reference
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Scenario 3 shows that mixing of was
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REFERENCES [1] International GT-MHR
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THE USE OF PB-BI EUTECTIC AS THE CO
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P d T = 6.0E+07, time at reactor fu
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The partial differential equations
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
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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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