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1. Introduction Spent fuels of modern nuclear reactors contain a rather large quantity of long-lived high-active wastes (plutonium, minor actinides (MA) and fission products (FP)). This amount of waste increases with the electricity production. If plutonium can be used as a fuel for reactors (both thermal and fast), ways should be found for decrease the amount of minor actinides and fission products. Therefore, the major challenge for the future nuclear energy system is the decrease of possible contamination of the environment by such wastes. Nevertheless, the existing reactors are able to solve these type of problems before development and operation of new promising nuclear systems. However, the implementation of thermal reactors for solving these problems is not efficient due to essential limitations of core physics. The use of traditional fast reactors allows solving the task partially. A homogeneous waste addition to the fuel makes it possible to utilise annually only 15% of all produced MAs in this period and less than 10% of long-lived FP. However, a noticeable degradation of neutronic parameters (increase in sodium void reactivity effect (SVRE) and decrease in Doppler-effect) requires a search for other decisions, more acceptable from a safety perspective. One of the possibilities involves the implementation of special irradiation devices (ID), which can be located either in radial or in axial blankets. In this case, the effect on core physics will be much less as compared with homogeneous recycling. But the efficiency of transmutation in these devices will be essentially lower. The efficiency of these devices can be improved by introducing a rather large quantity of moderator. This is related to the fact that practically all FPs have maximum cross-sections in the thermal region and MA cross-sections increase as well when shifting the neutron spectrum to the thermal region. Possibilities for MA and FP efficient transmutation in ID containing moderator are considered in this report for a fast power reactor of BN-800 type as an example. 2. MA burning in special devices located in the radial blanket Americium oxide located in a magnesium oxide inert matrix is considered as a fuel composition for MA burning. A ratio between volume fraction of americium oxide and magnesium oxide can be varied in such a way that it keeps the total americium loading in the ID. We noted that fast reactors have an important advantage over thermal reactors for burning minor actinides because their neutron flux is two orders as higher. However, in a fast spectrum, actinides have lower cross-sections compared to a thermal spectrum. On the basis of these two factors an idea appears to use moderated sub-assemblies (SAs) in fast reactors. In this case we conserve a rather high neutron flux and essentially increase the actinide cross-sections [1]. As an ID, we can consider a core SA in which part of the fuel pins are replaced by pins containing americium oxide in an inert matrix and others are replaced by pins containing a moderator. Varying the number of fuel pins with americium and moderator, one can change a moderator volume fraction in the SA. For a more essential moderator fraction increase, on can use a promising fuel pin design in which the central target material rod (of small diameter, with cladding or without it) is surrounded by a rather thick moderator layer. In this design, it is very easy to vary the ratio of fuel and moderator 220
volume fractions in a wide range conserving the fuel pin external diameter. This type SA design was used in further studies. One of the tasks of optimisation studies was a search for moderator material allowing a more efficient actinides transmutation, which all other things being the same. Figure 1 presents the dependency of the capture and fission cross-sections of some actinides on material type and Figure 2 – the dependency of the same cross-sections on moderator volume fraction in the fuel pin for zirconium hydride as the most efficient moderator. Figure 1. Dependency of actinide cross-sections on a moderator type 80 70 60 50 40 30 20 10 0 barn ZrH 2 MgH 2 CeH 3 σ cPu 240 σ fPu 241 σ cAm 241 σ fAm 242m σ cAm 243 σ fCm 243 Figure 2. Dependency of actinide cross-sections on a moderator volume fraction 120 barn 100 0 25 50 75 95 80 60 40 20 0 σ Pu 240 σ Pu 241 σ Am 241 σ Am 242m σ Am 243 σ Cm 243 We noted that the transmutation of americium in such ID would be worthwhile only if the radiotoxicity of wastes remaining after irradiation is much less than the radiotoxicity of non-irradiated americium. Figure 3 presents the change in waste radiotixicity for different ID burn-ups in reference to storage of non-irradiated americium 221
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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
Page 169 and 170: An extended “skeleton” for ADS
Page 171 and 172: • Fertile support (uranium) is no
Page 173: 7. Conclusions The TWG under the ch
Page 176 and 177: 1. Introduction The priorities for
Page 178 and 179: In the EURATOM Fourth Framework Pro
Page 180 and 181: Table 2. Cluster on transmutation-t
Page 182 and 183: 6. Community research for the perio
Page 184 and 185: REFERENCES [1] “Council Decision
Page 186 and 187: 1. Introduction Back in 1989, the O
Page 188 and 189: would need the continuation of tech
Page 190 and 191: individual isotopes as a function o
Page 192 and 193: Therefore, while there is continuin
Page 194 and 195: [9] OECD/NEA, Overview of Physics A
Page 197 and 198: RECENT TOPICS IN R&D FOR THE OMEGA
Page 199 and 200: Figure 1. Partitioning and transmut
Page 201 and 202: The present 4-GPP necessitates a pr
Page 203 and 204: 5. Concluding remarks In 1999, the
Page 205: REFERENCES [1] T. Mukaiyama, T. Tak
Page 208 and 209: 1. Introduction CIEMAT is actively
Page 210 and 211: adiotoxicity to be managed could al
Page 212 and 213: Figure 3. Mass composition of the d
Page 214 and 215: Figure 6. Fuel cycle assumed in the
Page 216 and 217: the 4 batches scheme, allowing to a
Page 218 and 219: Figure 11. Transmutation efficiency
Page 222 and 223: Figure 3. A change in radiotoxicity
Page 224 and 225: These dependencies are shown on Fig
Page 226 and 227: When increasing the moderator fract
Page 228 and 229: Even greater power increases are ob
Page 230 and 231: The effect of a moderator volume fr
Page 232 and 233: Table 11. Different isotopes contri
Page 234 and 235: Thus the transmutation of such FPs
Page 237 and 238: ASSESSMENT OF NUCLEAR POWER SCENARI
Page 239 and 240: elease probabilities. The time dist
Page 241 and 242: Table 2. Annual heavy nuclide contr
Page 243 and 244: Figure 3. Reduction of potential ra
Page 245 and 246: DISPOSAL OF PARTITIONING-TRANSMUTAT
Page 247 and 248: Figure 2. Decay heat from SNF 2000
Page 249 and 250: Figure 3. Shorter-lived HHR reposit
Page 251 and 252: 4. Management of low-heat, long-liv
Page 253 and 254: isotope from other caesium isotopes
Page 255 and 256: THE AMSTER CONCEPT J. Vergnes 1 , D
Page 257 and 258: Figure 1. Layout diagram of the mol
Page 259 and 260: Table 1. Definition of configuratio
Page 261 and 262: We therefore adopted a partial purg
Page 263 and 264: conceivable. Thus by increasing the
Page 265 and 266: 6. R&D needed to validate the AMSTE
Page 267: 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
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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
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
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Figure 1(b) shows the cases for the
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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 546 and 547:
neutron source, the reactor can mai
Page 548 and 549:
atoms. For fuel region Rf = 2.5 cm,
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Figure 3. Neutron flux spectra for
Page 552 and 553:
A possible way to maintain the k ef
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higher than 99% of 239 Pu, and high
Page 557 and 558:
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
Page 593 and 594:
HELIUM-COOLED REACTOR TECHNOLOGIES
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of its potential use in nuclear wea
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Figure 2. Neutron flux distribution
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atio. Given this rate of destructio
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Figure 5. Irradiated TRISO particle
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in ceramic-coated microspheres of t
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(LOCA) event. The effect on this fe
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Figure 13. Elevation AD-FMHR The fa
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Deep burn-up of 239 Pu and fissiona
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POSTER SESSION PARTITIONING M.J. Hu
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1. Introduction The study of the be
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Plutonium was simulated with the no
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The influence of uranium and pluton
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The influence of uranium and pluton
Page 624 and 625:
REFERENCES [1] I.I. Nazarenko, A.M.
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1. Introduction The long-term radio
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Ce Ce 3+ Cl - Cl 2 The voltammogram
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
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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
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efficiently and stable. This can be
Page 653 and 654:
Figure 1a. Zetapotential of NTA-mod
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Scheme 7. Magnetic silica particles
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
Page 664 and 665:
(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
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RECENT PROGRESSES ON PARTITIONING S
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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
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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,
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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
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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
Page 767 and 768:
Figure 11. Active target fraction (
Page 769 and 770:
d 2 σ Figure 14. Proton for n + Pb
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HIGH AND INTERMEDIATE ENERGY NUCLEA
Page 773 and 774:
eactions, since the pre-equilibrium
Page 775 and 776:
calculate the very short-lived radi
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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
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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
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
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3. Irradiation targets and irradiat
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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
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Table 3.Neutronics parameters of hy
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Figure 3. Neutron spectra averaged
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containing FA with B 4 C cladding i
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REFERENCES [1] ANSALDO Technical Re
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1. Introduction At present, there a
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target means a change in k and the
Page 828 and 829:
Following the normal procedure for
Page 830 and 831:
Acknowledgements This study has bee
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1. ADS description A conceptual des
Page 834 and 835:
Substitution of (9) into (8), and u
Page 836 and 837:
With the coupling LAHET + MCNP-DSP,
Page 838 and 839:
Figure 3. Comparison for 1 and 5 pu
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MOLTEN SALTS AS POSSIBLE FUEL FLUID
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2. The fuel salt for MSB concept Ma
Page 845 and 846:
and minor actinides must be removed
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4. Container material studies 4.1 F
Page 849 and 850:
management. The major developments
Page 851:
REFERENCES [1] H.J. MacPherson, Dev
Page 854 and 855:
1. Introduction The Energy Amplifie
Page 856 and 857:
Table 1. Main parameters of the EAD
Page 858 and 859:
Table 5. Neutron balance in the who
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Table 7. Neutron flux distributions
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Table 8. Displacement rates DPA/yea
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DEEP UNDERGROUND TRANSMUTOR (PASSIV
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passive state. By operating at a hi
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I have proposed using an accelerato
Page 871 and 872:
Figure 1. Layout of deep undergroun
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RADIATION CHARACTERISTICS OF PWR MO
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Table 1. Radiotoxicity of actinides
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RADIATION CHARACTERISTICS OF URANIU
Page 879 and 880:
Table 1. Radiotoxicity of actinides
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INTERNATIONAL CO-OPERATION ON CREAT
Page 883 and 884:
an international base to combine ef
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• 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
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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
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ORDER FORM OECD Nuclear Energy Agen
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