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neutron source, the reactor can maintain the neutron flux level and power during the life cycle of the fuel, and an almost constant k eff . Flexibility of the isotopic composition of the fuel. In the case of a critical reactor, the necessity to obtain a k eff equal to one during the burn-up of the fuel is a constrain to the fuel composition. In the case of the proposed open cycle PB reactor, the isotopic composition is fixed by the spent fuel discharged from the nuclear park in each country. The advantage of the ADS is that the external neutron source can maintain the neutron flux at the desired level, so that the composition of the fuel is less restricted than in a conventional critical reactor. The Pebble-bed transmutator [23] studied in this paper is an ADS, with an external spallation neutron source, created by interactions of high energy protons with a heavy metal, such as Pb. The fuel surrounding the target is contained inside of 3 cm of radius graphite spheres (the pebbles), having two regions [13-15]. The inner region contains carbide fuel kernels surrounded by a porous carbonaceous layer, called buffer. The buffer function is to absorb the gaseous fission products. It is coated with two layers of high density pyrolitic graphite and a layer of silicon carbide in between (TRISO), and the external part of the pebble is made of high purity graphite. The TRISO micro-spheres have a diameter of 0.9 mm [16-19]. In the neutronic calculations carried out in the present study, a homogeneous mixture of carbon and fuel atoms was assumed in the fuel region. We can do this [24] because the mean free path of the neutrons is larger than the size of the TRISO coated fuel particles, so for a neutron it is an homogeneous zone. The external radius of the pebble is 3 cm, and is a fixed parameter in these neutronic studies. An important characteristic of pebble-bed reactors is that it is possible to change the neutron spectra in the reactor by varying the radius of the inner region of the pebble assuming a constant mass of fuel. In the calculations below, 2 g per fuel sphere were assumed. The isotopic composition of the pebbles is given in Table 1. This isotopic composition corresponds to the actinides discharged from a LWR after an average burn-up of 30 MWd/kg-Metal. Only isotopes with a higher contribution to the radiotoxicity of the spent fuel have been chosen. The reactor is cooled by CO 2 , and the average temperature of the gas inside the core is 550 K, and the nominal outlet temperature is 800 K. This value is well below the disassociation threshold of CO 2 . The main characteristics of the PBT prototype studied are described in Table 2. The pebble-bed high temperature gas cooled reactors (HTGCR) has been designed already in the 60s and advanced concepts in the 70s. Some analysis on fast gas-cooled critical reactors [25] pointed out that decompression accidents (loss of coolant) would imply reactivity insertions leading to slightly supercritical states in a very short time (shorter than the estimated scram time, and without a significant Doppler effect in a core loaded with minor actinides). From the point of view of nuclear safety, such a type of critical transmutator would be impossible to license. However, in the case of an ADS, with an adequate margin of reactivity a transmutator of this type could be possible. The reactor will have continues refuelling and discharge of pebbles. It is important to notice that there is no intention of reprocessing the pebbles. That is, a once through transmutation scenario is imposed. 546
Table 1. Fuel composition Isotope Discharged mass LWR (gr/ton U) Isotopic composition 236 Np 5.312E-04 4.575E-08 237 Np 6.514E+02 5.610E-02 238 Pu 2.277E+02 1.961E-02 239 Pu 5.912E+03 5.092E-01 240 Pu 2.593E+03 2.233E-01 241 Pu 6.823E+02 5.867E-02 242 Pu 5.983E+02 5.153E-02 244 Pu 4.176E-02 3.597E-06 241 Am 7.651E+02 6.590E-02 Isotope Discharged mass LWR (g/t U) Isotopic composition 242m Am 2.452E+00 2.112E-04 243 Am 1.446E+02 1.245E-02 242 Cm 5.933E-03 5.110E-07 243 Cm 4.326E-01 3.726E-05 244 Cm 3.090E+01 2.661E-03 245 Cm 2.339E+00 2.014E-04 246 Cm 3.165E-01 2.726E-05 247 Cm 3.656E-03 3.149E-07 248 Cm 2.440E-04 2.101E-08 Table 2. Main specifications of a cylindrical prototype core Pebble-bed sub-critical prototype data Thermal power: 100 MW Porosity: 0.396 Fuel sphere diameter: 0.06 m Total gas volume: 0.835 m 3 Inner fuel zone diameter = 0.03 m Mean radius of the neutron source channel = 0.29 m Number of pebbles: 11 200 Active core height = 1.2 m Thermal power per pebble = 9 000 W Reactor core radius = 0.8 m Pebble outer surface: 113 cm 2 Reactor cross-section area = 1.74 m 2 Total outer surface of pebbles:125 m 2 Average gas flow cross-section: 0.6975 m 2 (for an active height of 1.2 m) Average heat flux: 8 × 10 5 W/m 2 Graphite reflector inner radius = 0.8 m Total pebble volume: 1.255 m 3 Reactor vessel inner radius = 1.00 m (20 cm thick graphite reflector) Total reactor volume: 2.09 m 3 Reactor vessel outer radius = 1.07 m 3. Effective cross-sections and transmutation rates The calculation model was made up from an infinite array of hexagonal channels. Inside each channel the pebble-bed spheres are stacked from bottom to top, in an infinite array. Each sphere contained an inner fuel region of variable diameter containing a mixture of graphite and TRISO coated fuel kernels. For the calculations, the fuel zone was assumed to be homogeneous. MCNPX code was used for all the neutronic calculations using ENDF-B/VI libraries. The average effective microscopic cross-sections obtained are given in Table 3. We can observe significant differences for different fuel radii. The average cross-section depends on the neutron spectra shown in Figure 3, which depends on the mass ratio between carbon and fuel 547
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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
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
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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
Page 492 and 493:
1. Introduction Since the 50s, nitr
Page 494 and 495:
A three dimensional model of a sub-
Page 496 and 497: Figure 4. Change in k-eigenvalue fo
Page 498 and 499: [4] Y. Arai et al., Experimental Re
Page 500 and 501: Nomenclature ADS: ATW: GT-MHR: LOF:
Page 502 and 503: Regarding switching off the beam, o
Page 504 and 505: Figure 3. Beam blocking 10 min (200
Page 506 and 507: Figure 7. A possible scenario for n
Page 508 and 509: [15] Greenspan E. et al., The Encap
Page 510 and 511: 1. Introduction In the EADF design
Page 512 and 513: Equation (6) can be improved by con
Page 514 and 515: where L is obtained by a summation
Page 516 and 517: Figure 1. The natural convection im
Page 518 and 519: Figure 4 shows the temperature tren
Page 520 and 521: [12] P.H. Wakker, Thermal Hydraulic
Page 522 and 523: 1. Introduction Research and develo
Page 524 and 525: Table 2. Core design parameters for
Page 526 and 527: 2.2 Representation of MA transmutat
Page 528 and 529: Figure 1(b) shows the cases for the
Page 530 and 531: It is found that the higher MA tran
Page 532 and 533: REFERENCES [1] T. Ikegami, H. Hayas
Page 534 and 535: 1. Introduction The management of t
Page 536 and 537: Table 1. Core performance of MA and
Page 538 and 539: Figure 3. Nuclear electricity capac
Page 540 and 541: 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
Page 548 and 549: atoms. For fuel region Rf = 2.5 cm,
Page 550 and 551: Figure 3. Neutron flux spectra for
Page 552 and 553: A possible way to maintain the k ef
Page 554 and 555: higher than 99% of 239 Pu, and high
Page 557 and 558: TRANSMUTATION OF NUCLEAR WASTES WIT
Page 559 and 560: Figure 1. PBT conceptual view Table
Page 561 and 562: 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
Page 567 and 568: 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
Page 575 and 576: 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
Page 590 and 591: 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
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1. Introduction The study of the be
Page 618 and 619:
Plutonium was simulated with the no
Page 620 and 621:
The influence of uranium and pluton
Page 622 and 623:
The influence of uranium and pluton
Page 624 and 625:
REFERENCES [1] I.I. Nazarenko, A.M.
Page 626 and 627:
1. Introduction The long-term radio
Page 628 and 629:
Ce Ce 3+ Cl - Cl 2 The voltammogram
Page 630 and 631:
Figure 3. Chronopotentiograms for t
Page 632 and 633:
Figure 4. Potentiometric titrations
Page 634 and 635:
Experimental solubilization tests w
Page 636 and 637:
[13] H. Flood T. Förland and K. Mo
Page 638 and 639:
1. Introduction The separation of l
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Figure 4. Synthesis of amides 11-15
Page 642 and 643:
1. Introduction Over the recent yea
Page 644 and 645:
2.3.2 Set-up We set up a single HFM
Page 646 and 647:
lower flow rates, Am(III) would be
Page 649 and 650:
THE POTENTIAL OF NANO- AND MICROPAR
Page 651 and 652:
efficiently and stable. This can be
Page 653 and 654:
Figure 1a. Zetapotential of NTA-mod
Page 655 and 656:
Scheme 7. Magnetic silica particles
Page 657:
[13] L.H. Delmau, N. Simon, M.J. Sc
Page 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
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
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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 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
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To get the proton (deuteron) energy
Page 765 and 766:
3.1 Corrections Several corrections
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Figure 11. Active target fraction (
Page 769 and 770:
d 2 σ Figure 14. Proton for n + Pb
Page 771 and 772:
HIGH AND INTERMEDIATE ENERGY NUCLEA
Page 773 and 774:
eactions, since the pre-equilibrium
Page 775 and 776:
calculate the very short-lived radi
Page 777 and 778:
cross-sections; the secondary react
Page 779 and 780:
All possible nuclear reactions will
Page 781 and 782:
A STUDY ON BURNABLE ABSORBER FOR A
Page 783 and 784:
2. Burnable absorber for HYPER 2.1
Page 785 and 786:
Table 2. One-group effective cross-
Page 787 and 788:
of the core, is directly determined
Page 789 and 790:
Figure 4. Required proton beam curr
Page 791 and 792:
Figure 8. 10 B depletion in HYPER-H
Page 793:
POSTER SESSION TRANSMUTATION SYSTEM
Page 796 and 797:
1. Introduction In the framework of
Page 798 and 799:
Φ >1 MeV = 1.0 10 13 to 1.0 x 10 1
Page 800 and 801:
3. Irradiation targets and irradiat
Page 802 and 803:
e transmuted in BR2 hence remain va
Page 804 and 805:
Table 6. Atom percent concentration
Page 806 and 807:
advantage, with respect to FRs, of
Page 809 and 810:
ENHANCEMENT OF ACTINIDE INCINERATIO
Page 811 and 812:
Here Σ fC , ( E) are the fission a
Page 813 and 814:
pellet and the steel cladding. In o
Page 815 and 816:
Table 3.Neutronics parameters of hy
Page 817 and 818:
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
Page 832 and 833:
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
Page 841 and 842:
MOLTEN SALTS AS POSSIBLE FUEL FLUID
Page 843 and 844:
2. The fuel salt for MSB concept Ma
Page 845 and 846:
and minor actinides must be removed
Page 847 and 848:
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
Page 856 and 857:
Table 1. Main parameters of the EAD
Page 858 and 859:
Table 5. Neutron balance in the who
Page 860 and 861:
Table 7. Neutron flux distributions
Page 862 and 863:
Table 8. Displacement rates DPA/yea
Page 865 and 866:
DEEP UNDERGROUND TRANSMUTOR (PASSIV
Page 867 and 868:
passive state. By operating at a hi
Page 869 and 870:
I have proposed using an accelerato
Page 871 and 872:
Figure 1. Layout of deep undergroun
Page 873 and 874:
RADIATION CHARACTERISTICS OF PWR MO
Page 875 and 876:
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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