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5. Laboratory research on electroseparation methods Laboratory research in the area of electro-separation methods is directed first of all at the determination of optimum conditions for residual uranium and fission product separation from fluoride melt and further on the selection of a suitable composition of the electrolyte based on fluoride salts mixture. As the fluoride melt should be able to dissolve sufficient amounts of plutonium and minor actinide elements, mixtures of LiF–NaF and LiF–NaF–KF type are in the foreground of interest. The assumed ability of sodium and potassium fluorides to form co-ordination compounds with transuranium element fluorides and so to significantly increase their solubility in the melt was the reason for choosing the mixtures mentioned. The research programme in this area is further directed to the determination and study of selected physicochemical properties of fluoride melts, particularly to the: • Solubility of lanthanides in molten fluorides. • Standard redox potentials of individual elements. • Melting points of the molten salt mixtures. • Density and viscosity of the supporting fuel matrices. • Data on corrosion resistance of structural materials. 6. Conclusion Research and development in the area of “Pyrochemical Partitioning” is carried out in the Czech Republic as a component of the national P&T programme within the framework of the “Transmutation” consortium. The programme is funded first of all by the Ministry of Industry and Trade and by the Radioactive Waste Repository Agency. The participants of the programme are, in addition to the NRI R ], SKODA Nuclear Machinery, Energovyzkum Brno, Nuclear Physics Institute of the Czech Academy of Sciences and Faculty of Nuclear Sciences and Physical Engineering of the Czech Technical University Prague. Experimental research work related to the development of pyrochemical technologies is concentrated mainly in the Fluorine Chemistry Department of the NRI R ]. The Czech national conception in the area of P&T research issues from the national power industry programme and from the Czech Power Company intentions of the extensive utilisation of nuclear power in our country. The Czech Republic, as a relatively small country, has an understandable interest in a wide integration into the solution of problems associated with spent nuclear fuel in the international context, first of all in co-operation with the EU member countries. Involvement into the 5th Framework Programme EC is an evidence of it, viz. in the area of “Pyrometallurgical Partitioning” where, for example, the PYROREP project is complementing very well with the research activities within the national programme framework. 312
REFERENCES [1] Uhlir J., Pyrochemical Reprocessing Technology and Molten Salt Transmutation Reactor Systems, OECD/NEA Workshop on Pyrochemical Separations, Avignon, France, March 14-16, 2000. [2] Uhlir J., An Experience on Dry Nuclear Fuel Reprocessing in the Czech Republic, Proc. 5th OECD/NEA Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Mol, Belgium, November 25-27, 1998, EUR 18898 EN, OECD/NEA (Nuclear Energy Agency), Paris, France, 1999. [3] Chochlovsky I et al., Molten Fluoride Salt Loop ADETTE-0 Experimental Programme, ADTTA99 – 3rd Int. Conf. on Accelerator Driven Transmutation Technologies and Applications, Prague, Czech Republic, June 7-11, 1999. 313
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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
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
Page 271 and 272: PARTITIONING-SEPARATION OF METAL IO
Page 273 and 274: The terpyridyl reagent (ligand L 1
Page 275 and 276: Figure 2. The synthesis of ADTPTZ a
Page 277 and 278: 2.4 Implications for partitioning T
Page 279 and 280: SEPARATION OF MINOR ACTINIDES FROM
Page 281 and 282: installed in a hot cell. The feed w
Page 283 and 284: the concentrations of U, Pu and Np
Page 285 and 286: Table 2 shows the recovery in the r
Page 287 and 288: PARTITIONING ANIONIC AGENTS BASED O
Page 289 and 290: which of these, the Co 3+ , Fe 3+ a
Page 291 and 292: This dianionic species must be extr
Page 293 and 294: Figure 6 Ph 2 P acetone PPh 2 H2 O
Page 295 and 296: Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
Page 297: [7] J. Rais and P. Selucky, Nucleon
Page 301 and 302: PYROCHEMICAL PROCESSING OF IRRADIAT
Page 303 and 304: The metallic cadmium product of the
Page 305 and 306: Figure 2. Schematic flow-sheet for
Page 307 and 308: R&D OF PYROCHEMICAL PARTITIONING IN
Page 309 and 310: (first of all pumps) for fluoride m
Page 311: 4. Research on material and equipme
Page 316 and 317: 1. Introduction The increasing inte
Page 318 and 319: Figure 2. Stainless steel box with
Page 320 and 321: Figure 4. U deposit on solid cathod
Page 322 and 323: Figure 7. Schematic flow of the cou
Page 324 and 325: actinide elements from spent (metal
Page 327 and 328: DEVELOPMENT OF PLUTONIUM RECOVERY P
Page 329 and 330: uranium dendrite and that uranium c
Page 331 and 332: Table 1. Conditions and results of
Page 333 and 334: Cathode potential went down to -1.6
Page 335 and 336: Figure 6. Change of LCC potential i
Page 337 and 338: Figure 9. Relation between Pu conce
Page 339 and 340: consideration described in the prec
Page 341: [13] Y. Arai, S. Fukushima, K. Shio
Page 345: SESSION IV BASIC PHYSICS, MATERIALS
Page 348 and 349: 1. Introduction The reduction of th
Page 350 and 351: agrees ours within limits of errors
Page 352 and 353: Figure 1. Thermal neutron capture c
Page 354 and 355: [18] A.P. Baerg, R.M. Bartholomew,
Page 356 and 357: 1. Introduction Nowadays it is well
Page 358 and 359: In order to describe the inter-nucl
Page 360 and 361: 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
Page 457:
[13] M. Akabori, M. Takano, A. Itoh
Page 460 and 461:
1. Introduction For the management
Page 462 and 463:
The scientific feasibility of pluto
Page 464 and 465:
Another option using a basis of sta
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6.2.1 Inert matrices 6.2.1.1 MgAl 2
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eached respectively 38.5% and 70% F
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Figure 4. Experiments for MA transm
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Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
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9.3 Programme for dedicated fuels F
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[14] R.J.M. Konings et al., The EFT
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1. Introduction An accelerator driv
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corresponding Pb-Bi velocity is 1.1
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the fission product target. The rod
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fuel rods are at the TRU assembly t
Page 489:
SESSION V TRANSMUTATION SYSTEMS AND
Page 492 and 493:
1. Introduction Since the 50s, nitr
Page 494 and 495:
A three dimensional model of a sub-
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Figure 4. Change in k-eigenvalue fo
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[4] Y. Arai et al., Experimental Re
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Nomenclature ADS: ATW: GT-MHR: LOF:
Page 502 and 503:
Regarding switching off the beam, o
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Figure 3. Beam blocking 10 min (200
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Figure 7. A possible scenario for n
Page 508 and 509:
[15] Greenspan E. et al., The Encap
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1. Introduction In the EADF design
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Equation (6) can be improved by con
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where L is obtained by a summation
Page 516 and 517:
Figure 1. The natural convection im
Page 518 and 519:
Figure 4 shows the temperature tren
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[12] P.H. Wakker, Thermal Hydraulic
Page 522 and 523:
1. Introduction Research and develo
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Table 2. Core design parameters for
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2.2 Representation of MA transmutat
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.,
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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
Page 561 and 562:
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
Page 573 and 574:
3 MYRRHA associated R&D programme F
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collaboration with Forschungszentru
Page 577:
• Industrial partners, in particu
Page 580 and 581:
1. Introduction The transmutation o
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Existing accelerators have been des
Page 584 and 585:
suggested to look for an innovative
Page 586 and 587:
Table 1. Main lead-bismuth eutectic
Page 588 and 589:
4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
Page 593 and 594:
HELIUM-COOLED REACTOR TECHNOLOGIES
Page 595 and 596:
of its potential use in nuclear wea
Page 597 and 598:
Figure 2. Neutron flux distribution
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atio. Given this rate of destructio
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Figure 5. Irradiated TRISO particle
Page 603 and 604:
in ceramic-coated microspheres of t
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(LOCA) event. The effect on this fe
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Figure 13. Elevation AD-FMHR The fa
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Deep burn-up of 239 Pu and fissiona
Page 613:
POSTER SESSION PARTITIONING M.J. Hu
Page 616 and 617:
1. Introduction The study of the be
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
Page 640 and 641:
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
Page 662 and 663:
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
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
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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
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[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
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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
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
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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
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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
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
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1. ADS description A conceptual des
Page 834 and 835:
Substitution of (9) into (8), and u
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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
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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
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• 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
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REFERENCES [1] White Book of Nuclea
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ORDER FORM OECD Nuclear Energy Agen
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