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1. Introduction For many accelerator driven system projects [1,2], lead has been chosen as a representative spallation target material. Therefore, Pb (p, X n), Pb (p, X p), Pb (p, X lcp) double differential crosssections (DDCS) are required with high priority for the development of simulation codes. These codes are used for feasibility studies and optimisation of such hybrid systems in which complex combinations of nuclear processes are involved. Combined with complementary Pb (n, X n), Pb (n, X p), Pb (n, X lcp) DDCS, these data represent the best test for evaluating the global capabilities of the models. In addition, such data provide important constraints which allow the predictive power of the codes to be improved in the 20-150 MeV energy range. In this context and in the framework of the Concerted Action “Lead for ADS” programme, we measure the DDCS of neutrons and light charged particles (p, d, t, 3 He, 4 He) produced in reactions induced by a proton beam, impinging on a lead target at 62.5 MeV. In this contribution we present results concerning only the neutrons. Figure 1. Simulation with GEANT of the experimental set-up geometry (see text) Target position 716
2. Experimental set-up The experiment was performed on the S-line of the CYCLONE facility in Louvain-la-Neuve. The lead target is 10.7 mg/cm 2 thick and the neutrons are detected using five DEMON large volume NE213 liquid scintillator counters [3]. The following table gives, for each counter, its angle theta relative to the beam and the distance between the target and its entrance window. DEMON counter theta (°) d (mm) 1 120 2 960 2 80 2 507 3 55 3 039 4 35 3 887 5 24 5 347 Each detector is surrounded by a lead cylinder installed inside a “BOMBARDE” barrel filled with paraffin and boron - materials that are efficient shields against background neutrons. Figure 2. Compilation of the measured DEMON detector efficiencies (symbols) compared to the predictions of the KSU code (black line) Due to the necessity of shielding the DEMON counters from the very high radiation background resulting from the proton beam dump, a wall made of concrete and paraffin is also built in the experimental area. Taking into account the experiment configuration (various materials and dimensions), the floor-space and the weight of concrete blocks, the wall dimensions is optimised performing GEANT simulations. The final wall geometry divides by a factor of twenty the background of the most exposed DEMON counter to the parasite neutron flux, resulting in a signalto-noise ratio of 2.1. The Figure 1 illustrates the efficiency of the shielding wall. It presents part of the geometry of the experimental set-up: the faraday cup placed at the end of the beam line and four DEMON counters imbedded in BOMBARDE barrels, and the shielding wall built between the forward DEMON counter and the beam dump. Dashed lines symbolise neutrons escaping from the 717
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Nuclear Development ACTINIDE AND FI
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FOREWORD The objective of the OECD/
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TABLE OF CONTENTS Foreword ........
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EXECUTIVE SUMMARY More than 160 par
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identified. In the fuel area, labor
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17:20-19:05 Session III: Partitioni
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Poster sessions Poster session: Par
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WELCOME ADDRESS Lucila Izquierdo Ge
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WELCOME ADDRESS Michel Hugon Co-ord
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WELCOME ADDRESS Philippe Savelli De
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developments. This will surely beco
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use of FBRs for transmutation toget
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view, i.e. better use of uranium an
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W. Forsberg proposes to reduce the
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1. From the open fuel cycle to the
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Figures 2 and 3 show the radiotoxic
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Denoting the transuranic (TRU) or m
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or, in terms of the fuel burn-up an
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quantities of LWR-MOX and FR-MOX wi
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view of the historic development, t
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Table 5. Assumptions for transmutat
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separating troublesome fission prod
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REFERENCES [1] L.H. Baetslé, Ch. D
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SESSION III Partitioning Chairs: J.
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OVERVIEW OF THE HYDROMETALLURGICAL
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2.1.3 Consequences Owing to the fac
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The extraction and separation mecha
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extractant was observed. As a conse
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2.3.2 Examples of strategies and
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3. Conclusions and perspectives 3.1
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SESSION IV Basic Physics, Materials
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TRANSMUTATION: A DECADE OF REVIVAL
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2.1 The IFR concept and the homogen
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2.3 Dedicated systems Making again
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compound “macro-dispersed” in M
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Figure 3. Sketch of ADS, liquid met
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3.3.2.1 The MEGAPIE project [40] ME
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3.3.2.2 The MUSE experiments The MU
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Figure 8. Comparison of the neutron
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Figure 9. Scenarios at equilibrium
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goals in this field. Since once-thr
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• The use of Thorium in PWRs alwa
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• Understanding of the role of AD
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[17] Y. Arai, T. Ogawa, Research on
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SESSION V Transmutation Systems and
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1. Introduction The term ADS compre
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• Safety should be “designed in
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3. Minor actinide and/or transurani
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Table 2. Values of Dj (neutron cons
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Table 4. Delayed neutron fraction I
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Figure 4. η (Neutrons released per
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Table 5. ADS Distinguishing feature
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While a favourable ADS safety featu
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Optimised mixes of MA and Pu can be
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Moreover, the fuel is where neutron
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REFERENCES [1] L. Van den Durpel et
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[19] D.C. Wade and E. Fujita, Trend
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POSTER SESSION Basic Physics: Nucle
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To conclude, this poster session in
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Five other papers related to ADS co
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SESSION I OVERVIEW OF NATIONAL AND
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1. Current activities for radioacti
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3.2 Results to date and analyses of
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3.2.5.2 JNC JNC is considering the
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4.6 Short-term increase in radiatio
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Annex 1 R&D scheme for partitioning
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Annex 3 Members of the Advisory Com
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plutonium can be recycled in pressu
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choices and the implementation of m
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1. Introduction Since the 5th Infor
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strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
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actually started to do so) because
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establishment of an international R
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The accelerator driven transmutatio
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substantiate this recommendation, s
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current, advanced and innovative nu
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ACCELERATOR DRIVEN SUB-CRITICAL SYS
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demonstration of feasibility of a E
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An extended “skeleton” for ADS
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• Fertile support (uranium) is no
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7. Conclusions The TWG under the ch
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1. Introduction The priorities for
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In the EURATOM Fourth Framework Pro
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Table 2. Cluster on transmutation-t
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6. Community research for the perio
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REFERENCES [1] “Council Decision
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1. Introduction Back in 1989, the O
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would need the continuation of tech
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individual isotopes as a function o
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Therefore, while there is continuin
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[9] OECD/NEA, Overview of Physics A
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RECENT TOPICS IN R&D FOR THE OMEGA
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Figure 1. Partitioning and transmut
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The present 4-GPP necessitates a pr
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5. Concluding remarks In 1999, the
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REFERENCES [1] T. Mukaiyama, T. Tak
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1. Introduction CIEMAT is actively
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adiotoxicity to be managed could al
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Figure 3. Mass composition of the d
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Figure 6. Fuel cycle assumed in the
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the 4 batches scheme, allowing to a
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Figure 11. Transmutation efficiency
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1. Introduction Spent fuels of mode
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Figure 3. A change in radiotoxicity
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These dependencies are shown on Fig
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When increasing the moderator fract
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Even greater power increases are ob
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The effect of a moderator volume fr
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Table 11. Different isotopes contri
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Thus the transmutation of such FPs
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ASSESSMENT OF NUCLEAR POWER SCENARI
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elease probabilities. The time dist
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Table 2. Annual heavy nuclide contr
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Figure 3. Reduction of potential ra
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DISPOSAL OF PARTITIONING-TRANSMUTAT
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Figure 2. Decay heat from SNF 2000
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Figure 3. Shorter-lived HHR reposit
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4. Management of low-heat, long-liv
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isotope from other caesium isotopes
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THE AMSTER CONCEPT J. Vergnes 1 , D
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Figure 1. Layout diagram of the mol
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Table 1. Definition of configuratio
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We therefore adopted a partial purg
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conceivable. Thus by increasing the
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6. R&D needed to validate the AMSTE
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SESSION III PARTITIONING J.P. Glatz
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PARTITIONING-SEPARATION OF METAL IO
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The terpyridyl reagent (ligand L 1
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Figure 2. The synthesis of ADTPTZ a
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2.4 Implications for partitioning T
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SEPARATION OF MINOR ACTINIDES FROM
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installed in a hot cell. The feed w
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the concentrations of U, Pu and Np
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Table 2 shows the recovery in the r
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PARTITIONING ANIONIC AGENTS BASED O
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which of these, the Co 3+ , Fe 3+ a
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This dianionic species must be extr
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Figure 6 Ph 2 P acetone PPh 2 H2 O
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Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
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[7] J. Rais and P. Selucky, Nucleon
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PYROCHEMICAL PROCESSING OF IRRADIAT
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The metallic cadmium product of the
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Figure 2. Schematic flow-sheet for
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R&D OF PYROCHEMICAL PARTITIONING IN
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(first of all pumps) for fluoride m
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4. Research on material and equipme
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REFERENCES [1] Uhlir J., Pyrochemic
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1. Introduction The increasing inte
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Figure 2. Stainless steel box with
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Figure 4. U deposit on solid cathod
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Figure 7. Schematic flow of the cou
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actinide elements from spent (metal
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DEVELOPMENT OF PLUTONIUM RECOVERY P
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uranium dendrite and that uranium c
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Table 1. Conditions and results of
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Cathode potential went down to -1.6
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Figure 6. Change of LCC potential i
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Figure 9. Relation between Pu conce
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consideration described in the prec
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[13] Y. Arai, S. Fukushima, K. Shio
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction The reduction of th
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agrees ours within limits of errors
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Figure 1. Thermal neutron capture c
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[18] A.P. Baerg, R.M. Bartholomew,
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1. Introduction Nowadays it is well
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In order to describe the inter-nucl
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kind of measurements allow to chara
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Figure 6. Two-dimensional cluster p
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Figure 8. Excitation functions for
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REFERENCES [1] D. Ridikas, thesis,
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1. Introduction Since 1991, the Com
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Experimental reactivity control tec
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Table 2. Neutron intensities Target
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experimental channels (horizontal a
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376
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Table 3. Planned experimental progr
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1. Introduction and benchmark speci
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neutrons. Since the neutron flux is
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Figure 2. Microscopic capture cross
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Figure 4. k eff variation in the st
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2.4 Neutron flux distribution One r
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etween the highest and the lowest v
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The isotope specific β eff values
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SESSION IV BASIC PHYSICS, MATERIALS
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1. Introduction Due to its excellen
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Figure 2. Tests scheme 0 340 h. 1 0
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Figure 4. Auger depth profile conce
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Figure 8. Auger depth profile conce
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deposited at the cold zone, and the
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inner layer grows inward from the o
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[8] V.M. Fedirko, O.I. Eliseeva, V.
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1. Introduction One of the main par
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3. Tantalum target irradiation The
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At 10-MeV neutron irradiation, radi
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1. Introduction HYPER (HYbrid Power
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this study, we used an orthogonal c
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Figure 5. Temperature distribution
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Figure 7. Thermal stress distributi
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FUEL/TARGET CONCEPTS FOR TRANSMUTAT
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(U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
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Figure 3. Left: Ceramograph of a (Z
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Figure 6. Left: ceramograph of a(Zr
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AMERICIUM TARGETS IN FAST REACTORS
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The reference case for all comparis
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It should be underlined that this c
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Cases Table 3. Heterogeneous recycl
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• A later step could be to add Cm
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RESEARCH ON NITRIDE FUEL AND PYROCH
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temperature for (Cm,Pu)N followed t
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Figure 1. Temperature dependence of
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The difference of two fuel pins exi
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In addition to the voltammetric stu
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2 wt% of Pu at 773 K. For the momen
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[13] M. Akabori, M. Takano, A. Itoh
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1. Introduction For the management
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The scientific feasibility of pluto
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Another option using a basis of sta
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6.2.1 Inert matrices 6.2.1.1 MgAl 2
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eached respectively 38.5% and 70% F
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Figure 4. Experiments for MA transm
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Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
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9.3 Programme for dedicated fuels F
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[14] R.J.M. Konings et al., The EFT
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1. Introduction An accelerator driv
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corresponding Pb-Bi velocity is 1.1
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the fission product target. The rod
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fuel rods are at the TRU assembly t
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SESSION V TRANSMUTATION SYSTEMS AND
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1. Introduction Since the 50s, nitr
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A three dimensional model of a sub-
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Figure 4. Change in k-eigenvalue fo
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[4] Y. Arai et al., Experimental Re
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Nomenclature ADS: ATW: GT-MHR: LOF:
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Regarding switching off the beam, o
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Figure 3. Beam blocking 10 min (200
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Figure 7. A possible scenario for n
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[15] Greenspan E. et al., The Encap
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1. Introduction In the EADF design
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Equation (6) can be improved by con
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where L is obtained by a summation
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Figure 1. The natural convection im
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Figure 4 shows the temperature tren
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[12] P.H. Wakker, Thermal Hydraulic
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1. Introduction Research and develo
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Table 2. Core design parameters for
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2.2 Representation of MA transmutat
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Figure 1(b) shows the cases for the
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It is found that the higher MA tran
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REFERENCES [1] T. Ikegami, H. Hayas
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1. Introduction The management of t
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Table 1. Core performance of MA and
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Figure 3. Nuclear electricity capac
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Table 3. Experimental items at PEF
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REFERENCES [1] Takano H., Akie H.,
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1. Introduction and background The
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neutron source, the reactor can mai
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atoms. For fuel region Rf = 2.5 cm,
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Figure 3. Neutron flux spectra for
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A possible way to maintain the k ef
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higher than 99% of 239 Pu, and high
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TRANSMUTATION OF NUCLEAR WASTES WIT
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Figure 1. PBT conceptual view Table
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very tight holders for fission frag
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5. Cooling system A preliminary des
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spectral densities [10,11] and can
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MYRRHA, A MULTI-PURPOSE ADS FOR R&D
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hexagonal assemblies of 122 mm plat
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to achieve the requested performanc
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3 MYRRHA associated R&D programme F
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collaboration with Forschungszentru
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• Industrial partners, in particu
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1. Introduction The transmutation o
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Existing accelerators have been des
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suggested to look for an innovative
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Table 1. Main lead-bismuth eutectic
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4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
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HELIUM-COOLED REACTOR TECHNOLOGIES
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of its potential use in nuclear wea
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Figure 2. Neutron flux distribution
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atio. Given this rate of destructio
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Figure 5. Irradiated TRISO particle
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in ceramic-coated microspheres of t
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(LOCA) event. The effect on this fe
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Figure 13. Elevation AD-FMHR The fa
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Deep burn-up of 239 Pu and fissiona
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POSTER SESSION PARTITIONING M.J. Hu
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1. Introduction The study of the be
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Plutonium was simulated with the no
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The influence of uranium and pluton
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The influence of uranium and pluton
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REFERENCES [1] I.I. Nazarenko, A.M.
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1. Introduction The long-term radio
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Ce Ce 3+ Cl - Cl 2 The voltammogram
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Figure 3. Chronopotentiograms for t
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Figure 4. Potentiometric titrations
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Experimental solubilization tests w
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[13] H. Flood T. Förland and K. Mo
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1. Introduction The separation of l
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Figure 4. Synthesis of amides 11-15
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1. Introduction Over the recent yea
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2.3.2 Set-up We set up a single HFM
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lower flow rates, Am(III) would be
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THE POTENTIAL OF NANO- AND MICROPAR
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efficiently and stable. This can be
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Figure 1a. Zetapotential of NTA-mod
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Scheme 7. Magnetic silica particles
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[13] L.H. Delmau, N. Simon, M.J. Sc
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1. Introduction 137 90 Extraction p
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Figure 3. Schematic drawing of the
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(24), 8-PhPO(OH)-O-COSAN (25), and
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
Page 675 and 676: hot tests (See Table2) was enough f
Page 677 and 678: 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: MEASUREMENTS OF PARTICULE EMISSION
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 742 and 743: 1. Introduction During the past few
Page 744 and 745: (same surface and 0.5 mm thickness)
Page 746 and 747: Figure 2. Dependence of the total a
Page 748 and 749: Figure 3. Neutron radiative capture
Page 750 and 751: [8] MCNP, A General Monte Carlo Cod
Page 752 and 753: 1. Introduction New reactors using
Page 754 and 755: Figure 1. Excited states of 209 Bi
Page 756 and 757: Figure 3. The fission probability o
Page 759 and 760: MEASUREMENT OF DOUBLE DIFFERENTIAL
Page 761 and 762: Figure 1. Global view of the experi
Page 763 and 764: To get the proton (deuteron) energy
Page 765 and 766: 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
Page 809 and 810:
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
Page 819 and 820:
containing FA with B 4 C cladding i
Page 821:
REFERENCES [1] ANSALDO Technical Re
Page 824 and 825:
1. Introduction At present, there a
Page 826 and 827:
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
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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
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REFERENCES [1] H.J. MacPherson, Dev
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1. Introduction The Energy Amplifie
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Table 1. Main parameters of the EAD
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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
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Figure 1. Layout of deep undergroun
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RADIATION CHARACTERISTICS OF PWR MO
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Table 1. Radiotoxicity of actinides
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RADIATION CHARACTERISTICS OF URANIU
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Table 1. Radiotoxicity of actinides
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INTERNATIONAL CO-OPERATION ON CREAT
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an international base to combine ef
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• Second topic: interaction of pr
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1. Introduction The role of acceler
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MEPI within the framework of Projec
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NEW ORIGINAL IDEAS ON ACCELERATOR D
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During conceptual investigations of
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delay, interface and computer. The
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2. Channel-vessel design of ADS bla
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Table 1. Characteristics of the ful
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[14] Karavaev G.N., Kiselev G.V., M
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1. Introduction The problem of nucl
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Table 3. Radiotoxicity in americium
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Table 5. Characteristics of station
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1. Introduction The atomic power en
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of lead-bismuth target are given in
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CRITICAL AND SUB-CRITICAL GT-MHRs F
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Table 1. Basic GT-MHR reactor param
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Figure 2. Typical change of the ave
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Scenario S4. This case is actually
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Figure 3. A change in radiotoxicity
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[13] P. Goberis, Modelling of Innov
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1. Introduction The Nuclear Enginee
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Some simplifications have been made
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Figure 3. Velocity vectors Some of
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Figure 6. Temperature evolution at
Page 938 and 939:
• Two main reasons can explain th
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1. Introduction Actually, we notice
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This problem can be solved by using
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The evaluations obtained in [2] hav
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REFERENCES [1] Management and Dispo
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1. Background Radiation background
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the long-term hazard of spent fuel,
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In a transmutation fuel cycle inclu
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Figure 4. Potential biological haza
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cooling prior to SF reprocessing an
Page 958:
REFERENCES [1] White Book of Nuclea
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ORDER FORM OECD Nuclear Energy Agen
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