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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
- Page 408 and 409: inner layer grows inward from the o
- Page 410 and 411: [8] V.M. Fedirko, O.I. Eliseeva, V.
- Page 412 and 413: 1. Introduction One of the main par
- Page 414 and 415: 3. Tantalum target irradiation The
- Page 416 and 417: At 10-MeV neutron irradiation, radi
- Page 418 and 419: 1. Introduction HYPER (HYbrid Power
- Page 420 and 421: this study, we used an orthogonal c
- Page 422 and 423: Figure 5. Temperature distribution
- Page 424 and 425: Figure 7. Thermal stress distributi
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- Page 429 and 430: (U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
- Page 431 and 432: Figure 3. Left: Ceramograph of a (Z
- Page 433 and 434: Figure 6. Left: ceramograph of a(Zr
- Page 435 and 436: AMERICIUM TARGETS IN FAST REACTORS
- Page 437 and 438: The reference case for all comparis
- Page 439 and 440: It should be underlined that this c
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- Page 443 and 444: • A later step could be to add Cm
- Page 445 and 446: RESEARCH ON NITRIDE FUEL AND PYROCH
- Page 447 and 448: temperature for (Cm,Pu)N followed t
- Page 449 and 450: Figure 1. Temperature dependence of
- Page 451 and 452: The difference of two fuel pins exi
- Page 453 and 454: In addition to the voltammetric stu
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- Page 461 and 462: concepts for plutonium consumption
- Page 463 and 464: Table 2. Objectives for transmutati
- Page 465 and 466: eing adjusted to take into account
- Page 467 and 468: 6.2.1.4 ZrO 2 Due to its low heat c
- Page 469 and 470: Figure 3a. 3D idealised meshing of
- Page 471 and 472: of 5% [24]. The target irradiation
- Page 473 and 474: for the Cochix irradiation (optimis
- Page 475 and 476: • Their high minor actinides (Np,
- Page 477 and 478: REFERENCES [1] P. Bernard, B. Barr
- Page 479 and 480: FISSION PRODUCT TARGET DESIGN FOR H
- Page 481 and 482: 2. General description of the core
- Page 483 and 484: 3. Basic characteristics of FP tran
- Page 485 and 486: Figure 6. FP target configuration a
- Page 487: Figure 7. Neutron energy spectrum f
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- Page 493 and 494: worth was calculated by removing al
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- Page 497 and 498: 4. Conclusions Having calculated th
- Page 499 and 500: ASPECTS OF SEVERE ACCIDENTS IN TRAN
- Page 501 and 502: direct cycle gas-cooled fast spectr
- Page 503 and 504: If an inlet blockage occurred in an
- Page 505 and 506: Another innovative approach is part
- Page 507 and 508: REFERENCES [1] US DOE, Generation I
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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
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REFERENCES [1] C. Rubbia et al., Co
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COMPARATIVE STUDY FOR MINOR ACTINID
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nitride fuel, reflection effect of
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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
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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
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Other original offer about sectiona
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concentration of lead in heavy wate
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[5] Kolesov V.P., Gughovski B.Ya.,
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CONDITIONS OF PLUTONIUM, AMERICIUM
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The further increase after 500 days
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decrease. Total actinide amount muc
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DEMONSTRATION ACCELERATOR DRIVEN CO
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Thus, stable nuclides will be forme
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Table 4. Characteristics of linac w
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1. Introduction Nuclear waste radio
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Figure 1. Lengthwise section view o
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Scenario S0. This is our reference
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Scenario 3 shows that mixing of was
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REFERENCES [1] International GT-MHR
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THE USE OF PB-BI EUTECTIC AS THE CO
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P d T = 6.0E+07, time at reactor fu
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The partial differential equations
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Figure 5. Core and heat exchanger p
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with the STAR-CD results is still t
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ONE WAY TO CREATE PROLIFERATION-PRO
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By supposing that FA manufacturing
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exponentially reduces with rather l
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Thus, 232 U generation by only one
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TRANSMUTATION OF LONG-LIVED NUCLIDE
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In the existing open fuel cycle, in
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then include 31% of Np, 66% of Am a
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Let us discuss the radiation balanc
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Higher requirements for the cleanin
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RW disposal is multibarrier configu
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ALSO AVAILABLE ECONOMIC AND TECHNIC
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