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Table 2. Cluster on transmutation-technological support Acronym Subject of research Co-ordinator (country) SPIRE TECLA CONFIRM THORIUM CYCLE Effects of neutron and proton irradiation in steels Materials and thermohydraulics for lead alloys Uranium free nitride fuel irradiation and modelling Development of thorium cycle for PWR and ADS Number of partners Duration (months) EC funding (Million ) CEA (F) 10 48 2.3 ENEA (I) 16 36 2.5 KTH (S) 7 48 1.0 NRG (NL) 7 48 1.2 Finally, three projects are grouped in the cluster on transmutation-basic studies (see Table 3). The MUSE project aims to provide validated analytical tools for sub-critical neutronics including recommended methods, data and a reference calculation tool for ADS study. The experiments will be carried out by coupling a pulsed neutron generator to the MASURCA facility loaded with different fast neutron multiplying sub-critical configurations. The configurations will have MOX fuel with various coolants (sodium, lead and gas). Cross-comparison of codes and data is foreseen. Experimental reactivity control techniques, related to sub-critical operation, will be developed. The last two projects are dealing with nuclear data, one at medium and high energy required for the ADS engineering design including the spallation target (HINDAS), and the other encompassing the lower energy in resonance regions required for transmutation (n-TOF-ND-ADS). The objective of the HINDAS project is to collect most of the nuclear data necessary for ADS application. This will be achieved by basic cross section measurements at different European facilities, nuclear model simulations and data evaluations in the 20-200 MeV energy region and beyond. Iron, lead and uranium have been chosen to have a representative coverage of the periodic table, of the different reaction mechanisms and, in the case of iron and lead, of the various materials used for ADS. The n-TOF-ND-ADS project aims at the production, evaluation and dissemination of neutron cross sections for most of the radioisotopes (actinides and long-lived fission products) considered for transmutation in the energy range from 1 eV up to 250 MeV. The project is starting with the design and development of high performance detectors and fast data acquisition systems. Measurements will be carried out at the TOF facility at CERN, at the GELINA facility in Geel and using other neutron sources located at different EU laboratories. Finally, an integrated software environment will be developed at CERN for the storage, retrieval and processing of nuclear data in their various formats. 180
Table 3. Cluster on transmutation-basic studies Acronym Subject of research Co-ordinator (country) Number of Partners Duration (months) EC funding (Million ) MUSE Experiments for subcritical CEA (F) 13 36 2.0 neutronics validation HINDAS High and intermediate UCL (B) 16 36 2.1 energy nuclear data for ADS n-TOF-ND-ADS ADS nuclear data CERN 18 36 2.4 The second call for proposals has been published in October 2000 with a deadline in January 2001. This call has been targeted on the areas, which were not sufficiently well covered by the projects selected after the first call, such as preliminary engineering design studies for an ADS demonstrator and technological support. A new item, networking, has been included in this call. But the areas of chemical separation and basic studies are not included, as they were well covered in the first call. 5. ADS related research activities in the framework of the International Science and Technology Centre (ISTC) The International Science and Technology Centre (ISTC) was established by an international agreement in November 1992 as a non-proliferation programme through science co-operation. It is an intergovernmental organisation grouping the European Union, Japan, the USA, Norway, the Republic of Korea, which are the funding parties, and some countries of the Commonwealth of Independent States (CIS): the Russian Federation, Armenia, Belarus, Georgia, Kazakhstan and Kyrgyzstan. The ISTC finances and monitors science and technology projects to ensure that the CIS scientists, especially those with expertise in developing weapons of mass destruction, are offered the opportunity to use their skills in the civilian fields. A Contact Expert Group (CEG) on ADS related ISTC projects has been created in January 1998. Its main objectives are to review proposals in this field and to give recommendations for their funding to the ISTC Governing Board, to monitor the funded projects and to promote the possibilities of future or joint research projects through the ISTC. Five topics have been identified for the ADS related projects: (i) accelerator technology, (ii) basic nuclear and material data and neutronics of ADS, (iii) targets and materials, (iv) fuels related to ADS and (v) aqueous separation chemistry. Because the funding parties primarily respond to local scientific/political interests and pressure, it was decided in January 2000 to reorganise the CEG into “local” CEGs (EU, Japan, Republic of Korea and USA) with some inter-co-ordination between them. This inter-co-ordination should foster exchange of information between ISTC projects in the same field, even if they are supported by different funding parties. The EU CEG should develop co-operation between ISTC and FP5 EU funded projects. In fact, collaboration has already started between EU scientists, not necessarily belonging to the CEG, and CIS research teams both in the preparation of ISTC proposals and in the follow-up of projects in some specific areas. Links with FP5 projects will be established, once the projects have actually started. An area where the co-operation between ISTC and FP5 EU funded projects could be improved is that of basic nuclear data for ADS. 181
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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
Page 129: SESSION I OVERVIEW OF NATIONAL AND
Page 132 and 133: 1. Current activities for radioacti
Page 134 and 135: 3.2 Results to date and analyses of
Page 136 and 137: 3.2.5.2 JNC JNC is considering the
Page 138 and 139: 4.6 Short-term increase in radiatio
Page 140 and 141: Annex 1 R&D scheme for partitioning
Page 142 and 143: Annex 3 Members of the Advisory Com
Page 144 and 145: plutonium can be recycled in pressu
Page 146 and 147: choices and the implementation of m
Page 148 and 149: 1. Introduction Since the 5th Infor
Page 150 and 151: strata” approach which would invo
Page 153 and 154: IAEA ACTIVITIES IN THE AREA OF EMER
Page 155 and 156: actually started to do so) because
Page 157 and 158: establishment of an international R
Page 159 and 160: The accelerator driven transmutatio
Page 161 and 162: substantiate this recommendation, s
Page 163 and 164: current, advanced and innovative nu
Page 165 and 166: ACCELERATOR DRIVEN SUB-CRITICAL SYS
Page 167 and 168: demonstration of feasibility of a E
Page 169 and 170: An extended “skeleton” for ADS
Page 171 and 172: • Fertile support (uranium) is no
Page 173: 7. Conclusions The TWG under the ch
Page 176 and 177: 1. Introduction The priorities for
Page 178 and 179: In the EURATOM Fourth Framework Pro
Page 182 and 183: 6. Community research for the perio
Page 184 and 185: REFERENCES [1] “Council Decision
Page 186 and 187: 1. Introduction Back in 1989, the O
Page 188 and 189: would need the continuation of tech
Page 190 and 191: individual isotopes as a function o
Page 192 and 193: Therefore, while there is continuin
Page 194 and 195: [9] OECD/NEA, Overview of Physics A
Page 197 and 198: RECENT TOPICS IN R&D FOR THE OMEGA
Page 199 and 200: Figure 1. Partitioning and transmut
Page 201 and 202: The present 4-GPP necessitates a pr
Page 203 and 204: 5. Concluding remarks In 1999, the
Page 205: REFERENCES [1] T. Mukaiyama, T. Tak
Page 208 and 209: 1. Introduction CIEMAT is actively
Page 210 and 211: adiotoxicity to be managed could al
Page 212 and 213: Figure 3. Mass composition of the d
Page 214 and 215: Figure 6. Fuel cycle assumed in the
Page 216 and 217: the 4 batches scheme, allowing to a
Page 218 and 219: Figure 11. Transmutation efficiency
Page 220 and 221: 1. Introduction Spent fuels of mode
Page 222 and 223: Figure 3. A change in radiotoxicity
Page 224 and 225: These dependencies are shown on Fig
Page 226 and 227: When increasing the moderator fract
Page 228 and 229: 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
Page 546 and 547:
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
Page 624 and 625:
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
Page 646 and 647:
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
Page 653 and 654:
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
Page 660 and 661:
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
Page 666 and 667:
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
Page 681:
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
Page 688 and 689:
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
Page 722 and 723:
1. Introduction Intermediate-energy
Page 724 and 725:
Table 1. Relative neutron-induced c
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elow about 70 MeV [24] , where σ n
Page 728 and 729:
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
Page 735 and 736:
Figure 1. Scheme of the new code Z
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Figure 3. Neutron-induced fission c
Page 739:
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
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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
Page 798 and 799:
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
Page 821:
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
Page 828 and 829:
Following the normal procedure for
Page 830 and 831:
Acknowledgements This study has bee
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1. ADS description A conceptual des
Page 834 and 835:
Substitution of (9) into (8), and u
Page 836 and 837:
With the coupling LAHET + MCNP-DSP,
Page 838 and 839:
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
Page 845 and 846:
and minor actinides must be removed
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4. Container material studies 4.1 F
Page 849 and 850:
management. The major developments
Page 851:
REFERENCES [1] H.J. MacPherson, Dev
Page 854 and 855:
1. Introduction The Energy Amplifie
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Table 1. Main parameters of the EAD
Page 858 and 859:
Table 5. Neutron balance in the who
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Table 7. Neutron flux distributions
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Table 8. Displacement rates DPA/yea
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DEEP UNDERGROUND TRANSMUTOR (PASSIV
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passive state. By operating at a hi
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I have proposed using an accelerato
Page 871 and 872:
Figure 1. Layout of deep undergroun
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RADIATION CHARACTERISTICS OF PWR MO
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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 906 and 907:
1. Introduction The problem of nucl
Page 908 and 909:
Table 3. Radiotoxicity in americium
Page 910 and 911:
Table 5. Characteristics of station
Page 912 and 913:
1. Introduction The atomic power en
Page 914 and 915:
of lead-bismuth target are given in
Page 917 and 918:
CRITICAL AND SUB-CRITICAL GT-MHRs F
Page 919 and 920:
Table 1. Basic GT-MHR reactor param
Page 921 and 922:
Figure 2. Typical change of the ave
Page 923 and 924:
Scenario S4. This case is actually
Page 925 and 926:
Figure 3. A change in radiotoxicity
Page 927:
[13] P. Goberis, Modelling of Innov
Page 930 and 931:
1. Introduction The Nuclear Enginee
Page 932 and 933:
Some simplifications have been made
Page 934 and 935:
Figure 3. Velocity vectors Some of
Page 936 and 937:
Figure 6. Temperature evolution at
Page 938 and 939:
• Two main reasons can explain th
Page 940 and 941:
1. Introduction Actually, we notice
Page 942 and 943:
This problem can be solved by using
Page 944 and 945:
The evaluations obtained in [2] hav
Page 946 and 947:
REFERENCES [1] Management and Dispo
Page 948 and 949:
1. Background Radiation background
Page 950 and 951:
the long-term hazard of spent fuel,
Page 952 and 953:
In a transmutation fuel cycle inclu
Page 954 and 955:
Figure 4. Potential biological haza
Page 956 and 957:
cooling prior to SF reprocessing an
Page 958:
REFERENCES [1] White Book of Nuclea
Page 961 and 962:
ORDER FORM OECD Nuclear Energy Agen
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