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NEUTRON RADIATIVE CAPTURE CROSS-SECTION OF 232 Th IN THE ENERGY RANGE FROM 0.06 TO 2 MeV D. Karamanis 1 , M. Petit 1 , S. Andriamonje 1 , G. Barreau 1 , M. Bercion 1 , A. Billebaud 2 ,B. Blank 1 , S. Czajkowski 1 , R. Del Moral 1 , J. Giovinazzo 1 , V. Lacoste 3 , C. Marchand 1 ,L. Perrot 2 , M. Pravikoff 1 , J.C. Thomas 1 1 CEN/Bordeaux-Gradignan, France 2 ISN, Grenoble, France 3 CERN, Geneva, Switzerland Abstract Neutron capture cross-section of 232 Th have been measured relative to σ(n,γ) for 197 Au and σ(n,f) for 235 U in the energy range from 60 keV to 2 MeV. Neutrons were produced by the 7 Li(p,n) and T(p,n) reactions at the 4 MV Van de Graaff Accelerator of CEN/Bordeaux. The activation technique was used and the cross-section was measured relative to the 197 Au(n,γ) standard cross-section up to 1 MeV. Above this energy, the reaction 235 U(n,f) was also used as a second standard and the fission fragments were detected with a photovoltaic cell. The results after applying the appropriate corrections indicate that the cross-sections are close to the JENDL-3 database values up to 800 keV and over 1.4 MeV. For energies in the intermediate range, values are slightly lower to the ones from all the libraries. 741
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Nuclear Development ACTINIDE AND FI
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FOREWORD The objective of the OECD/
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TABLE OF CONTENTS Foreword ........
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EXECUTIVE SUMMARY More than 160 par
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identified. In the fuel area, labor
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17:20-19:05 Session III: Partitioni
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Poster sessions Poster session: Par
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WELCOME ADDRESS Lucila Izquierdo Ge
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WELCOME ADDRESS Michel Hugon Co-ord
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WELCOME ADDRESS Philippe Savelli De
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developments. This will surely beco
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use of FBRs for transmutation toget
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view, i.e. better use of uranium an
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W. Forsberg proposes to reduce the
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1. From the open fuel cycle to the
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Figures 2 and 3 show the radiotoxic
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Denoting the transuranic (TRU) or m
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or, in terms of the fuel burn-up an
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quantities of LWR-MOX and FR-MOX wi
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view of the historic development, t
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Table 5. Assumptions for transmutat
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separating troublesome fission prod
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REFERENCES [1] L.H. Baetslé, Ch. D
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SESSION III Partitioning Chairs: J.
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OVERVIEW OF THE HYDROMETALLURGICAL
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2.1.3 Consequences Owing to the fac
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The extraction and separation mecha
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extractant was observed. As a conse
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2.3.2 Examples of strategies and
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3. Conclusions and perspectives 3.1
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SESSION IV Basic Physics, Materials
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TRANSMUTATION: A DECADE OF REVIVAL
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2.1 The IFR concept and the homogen
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2.3 Dedicated systems Making again
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compound “macro-dispersed” in M
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Figure 3. Sketch of ADS, liquid met
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3.3.2.1 The MEGAPIE project [40] ME
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3.3.2.2 The MUSE experiments The MU
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Figure 8. Comparison of the neutron
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Figure 9. Scenarios at equilibrium
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goals in this field. Since once-thr
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• The use of Thorium in PWRs alwa
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• Understanding of the role of AD
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[17] Y. Arai, T. Ogawa, Research on
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SESSION V Transmutation Systems and
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1. Introduction The term ADS compre
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• Safety should be “designed in
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3. Minor actinide and/or transurani
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Table 2. Values of Dj (neutron cons
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Table 4. Delayed neutron fraction I
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Figure 4. η (Neutrons released per
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Table 5. ADS Distinguishing feature
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While a favourable ADS safety featu
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Optimised mixes of MA and Pu can be
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Moreover, the fuel is where neutron
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REFERENCES [1] L. Van den Durpel et
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[19] D.C. Wade and E. Fujita, Trend
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POSTER SESSION Basic Physics: Nucle
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To conclude, this poster session in
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Five other papers related to ADS co
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SESSION I OVERVIEW OF NATIONAL AND
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1. Current activities for radioacti
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3.2 Results to date and analyses of
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3.2.5.2 JNC JNC is considering the
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4.6 Short-term increase in radiatio
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Annex 1 R&D scheme for partitioning
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Annex 3 Members of the Advisory Com
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plutonium can be recycled in pressu
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choices and the implementation of m
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1. Introduction Since the 5th Infor
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strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
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actually started to do so) because
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establishment of an international R
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The accelerator driven transmutatio
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substantiate this recommendation, s
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current, advanced and innovative nu
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ACCELERATOR DRIVEN SUB-CRITICAL SYS
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demonstration of feasibility of a E
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An extended “skeleton” for ADS
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• Fertile support (uranium) is no
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7. Conclusions The TWG under the ch
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1. Introduction The priorities for
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In the EURATOM Fourth Framework Pro
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Table 2. Cluster on transmutation-t
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6. Community research for the perio
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REFERENCES [1] “Council Decision
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1. Introduction Back in 1989, the O
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would need the continuation of tech
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individual isotopes as a function o
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Therefore, while there is continuin
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[9] OECD/NEA, Overview of Physics A
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RECENT TOPICS IN R&D FOR THE OMEGA
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Figure 1. Partitioning and transmut
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The present 4-GPP necessitates a pr
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5. Concluding remarks In 1999, the
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REFERENCES [1] T. Mukaiyama, T. Tak
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1. Introduction CIEMAT is actively
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adiotoxicity to be managed could al
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Figure 3. Mass composition of the d
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Figure 6. Fuel cycle assumed in the
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the 4 batches scheme, allowing to a
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Figure 11. Transmutation efficiency
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1. Introduction Spent fuels of mode
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Figure 3. A change in radiotoxicity
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These dependencies are shown on Fig
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When increasing the moderator fract
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Even greater power increases are ob
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The effect of a moderator volume fr
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Table 11. Different isotopes contri
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Thus the transmutation of such FPs
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ASSESSMENT OF NUCLEAR POWER SCENARI
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elease probabilities. The time dist
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Table 2. Annual heavy nuclide contr
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Figure 3. Reduction of potential ra
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DISPOSAL OF PARTITIONING-TRANSMUTAT
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Figure 2. Decay heat from SNF 2000
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Figure 3. Shorter-lived HHR reposit
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4. Management of low-heat, long-liv
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isotope from other caesium isotopes
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THE AMSTER CONCEPT J. Vergnes 1 , D
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Figure 1. Layout diagram of the mol
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Table 1. Definition of configuratio
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We therefore adopted a partial purg
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conceivable. Thus by increasing the
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6. R&D needed to validate the AMSTE
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SESSION III PARTITIONING J.P. Glatz
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PARTITIONING-SEPARATION OF METAL IO
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The terpyridyl reagent (ligand L 1
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Figure 2. The synthesis of ADTPTZ a
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2.4 Implications for partitioning T
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SEPARATION OF MINOR ACTINIDES FROM
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installed in a hot cell. The feed w
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the concentrations of U, Pu and Np
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Table 2 shows the recovery in the r
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PARTITIONING ANIONIC AGENTS BASED O
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which of these, the Co 3+ , Fe 3+ a
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This dianionic species must be extr
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Figure 6 Ph 2 P acetone PPh 2 H2 O
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Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
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[7] J. Rais and P. Selucky, Nucleon
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PYROCHEMICAL PROCESSING OF IRRADIAT
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The metallic cadmium product of the
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Figure 2. Schematic flow-sheet for
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R&D OF PYROCHEMICAL PARTITIONING IN
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(first of all pumps) for fluoride m
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4. Research on material and equipme
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REFERENCES [1] Uhlir J., Pyrochemic
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1. Introduction The increasing inte
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Figure 2. Stainless steel box with
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Figure 4. U deposit on solid cathod
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Figure 7. Schematic flow of the cou
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actinide elements from spent (metal
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DEVELOPMENT OF PLUTONIUM RECOVERY P
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uranium dendrite and that uranium c
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Table 1. Conditions and results of
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Cathode potential went down to -1.6
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Figure 6. Change of LCC potential i
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Figure 9. Relation between Pu conce
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consideration described in the prec
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[13] Y. Arai, S. Fukushima, K. Shio
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction The reduction of th
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agrees ours within limits of errors
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Figure 1. Thermal neutron capture c
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[18] A.P. Baerg, R.M. Bartholomew,
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1. Introduction Nowadays it is well
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In order to describe the inter-nucl
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kind of measurements allow to chara
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Figure 6. Two-dimensional cluster p
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Figure 8. Excitation functions for
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REFERENCES [1] D. Ridikas, thesis,
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1. Introduction Since 1991, the Com
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Experimental reactivity control tec
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Table 2. Neutron intensities Target
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experimental channels (horizontal a
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376
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Table 3. Planned experimental progr
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1. Introduction and benchmark speci
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neutrons. Since the neutron flux is
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Figure 2. Microscopic capture cross
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Figure 4. k eff variation in the st
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2.4 Neutron flux distribution One r
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etween the highest and the lowest v
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The isotope specific β eff values
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Due to its excellen
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Figure 2. Tests scheme 0 340 h. 1 0
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Figure 4. Auger depth profile conce
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Figure 8. Auger depth profile conce
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deposited at the cold zone, and the
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inner layer grows inward from the o
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[8] V.M. Fedirko, O.I. Eliseeva, V.
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1. Introduction One of the main par
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3. Tantalum target irradiation The
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At 10-MeV neutron irradiation, radi
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1. Introduction HYPER (HYbrid Power
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this study, we used an orthogonal c
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Figure 5. Temperature distribution
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Figure 7. Thermal stress distributi
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FUEL/TARGET CONCEPTS FOR TRANSMUTAT
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(U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
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Figure 3. Left: Ceramograph of a (Z
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Figure 6. Left: ceramograph of a(Zr
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AMERICIUM TARGETS IN FAST REACTORS
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The reference case for all comparis
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It should be underlined that this c
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Cases Table 3. Heterogeneous recycl
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• A later step could be to add Cm
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RESEARCH ON NITRIDE FUEL AND PYROCH
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temperature for (Cm,Pu)N followed t
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Figure 1. Temperature dependence of
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The difference of two fuel pins exi
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In addition to the voltammetric stu
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2 wt% of Pu at 773 K. For the momen
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[13] M. Akabori, M. Takano, A. Itoh
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
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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
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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
Page 534 and 535:
1. Introduction The management of t
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Table 1. Core performance of MA and
Page 538 and 539:
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
Page 559 and 560:
Figure 1. PBT conceptual view Table
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very tight holders for fission frag
Page 563 and 564:
5. Cooling system A preliminary des
Page 565 and 566:
spectral densities [10,11] and can
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MYRRHA, A MULTI-PURPOSE ADS FOR R&D
Page 569 and 570:
hexagonal assemblies of 122 mm plat
Page 571 and 572:
to achieve the requested performanc
Page 573 and 574:
3 MYRRHA associated R&D programme F
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collaboration with Forschungszentru
Page 577:
• Industrial partners, in particu
Page 580 and 581:
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
Page 597 and 598:
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
Page 613:
POSTER SESSION PARTITIONING M.J. Hu
Page 616 and 617:
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
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
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[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
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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
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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
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Scheme 7. Magnetic silica particles
Page 657:
[13] L.H. Delmau, N. Simon, M.J. Sc
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1. Introduction 137 90 Extraction p
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Figure 3. Schematic drawing of the
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(24), 8-PhPO(OH)-O-COSAN (25), and
Page 666 and 667:
REFERENCES [1] Kyrš M., +H PiQHN S
Page 668 and 669:
1. Introduction A heavy-water CANDU
Page 670 and 671:
These data show that fuel lifetime
Page 673 and 674:
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
Page 679 and 680:
6. Conclusion Declassification of t
Page 681:
POSTER SESSION BASIC PHYSICS: NUCLE
Page 684 and 685:
1. Introduction Among the large num
Page 686 and 687:
The simulation of the spallation pr
Page 688 and 689:
Table 1. Parameters of the two coll
Page 690 and 691: Figure 4. Radial distribution of th
Page 692 and 693: 6. The neutron escape line The comm
Page 694 and 695: Figure 7. Neutron background at the
Page 697 and 698: RECENT CAPTURE CROSS-SECTIONS VALID
Page 699 and 700: Figure 1. The GENEPI accelerator an
Page 701 and 702: 2.3.3 Neutron flux measurements •
Page 703 and 704: Figure 6. Time spectrum of 3 He gas
Page 705 and 706: 4. Analysis 4.1 Background subtract
Page 707 and 708: Figure 11. ENDF/B-VI, JEF2.2 and JE
Page 709 and 710: DOUBLE DIFFERENTIAL CROSS-SECTION F
Page 711 and 712: 3. Conclusion Double differential c
Page 713 and 714: Figure 3. Preliminary results of do
Page 715 and 716: MEASUREMENTS OF PARTICULE EMISSION
Page 717 and 718: 2. Experimental set-up The experime
Page 719: 4. Results Figure 3 presents neutro
Page 722 and 723: 1. Introduction Intermediate-energy
Page 724 and 725: Table 1. Relative neutron-induced c
Page 726 and 727: elow about 70 MeV [24] , where σ n
Page 728 and 729: Since for sub-actinides Γ f /Γ n
Page 730 and 731: [10] V.P. Eismont, A.V. Prokofiev,
Page 733 and 734: NUCLEON-INDUCED FISSION CROSS-SECTI
Page 735 and 736: Figure 1. Scheme of the new code Z
Page 737 and 738: Figure 3. Neutron-induced fission c
Page 739: REFERENCES [1] J. Raynal, Proceedin
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
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4. Possible technical tasks on crea
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ON NECESSITY OF CREATION OF ACCELER
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Table 2. Transmutation of 99 Tc wit
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Another important problem concernin
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1. Introduction During the last yea
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Other original proposal of the indi
Page 898 and 899:
Other original offer about sectiona
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concentration of lead in heavy wate
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[5] Kolesov V.P., Gughovski B.Ya.,
Page 905 and 906:
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
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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
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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