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2.4 Neutron flux distribution One radial flux distribution corresponding to the mid-plane and two axial flux distributions corresponding, respectively, to the centre of the target and the fuel zone were requested. Considerable differences between the participants are observed, especially for the radial neutron flux distribution and for the axial flux distribution in the target zone. In particular, ENDF-based results (ANL and RIT) estimate by far the lowest neutron flux through the target. The discrepancies are also significant in the fuel region, where differences in flux level and in peak flux position appear. These discrepancies can be partially explained by the different level of sub-criticality: a system with a lower k eff needs more external neutrons in order to maintain the chain reaction. This results in a more peaked axial flux in the target, at the interface with the duct, and a displacement of the axial flux peak in the fuel towards the upper part of the core. An additional study was performed with ERANOS in order to assess the impact of the k eff value on the neutron flux distribution. By modifying appropriately the ν values for reproducing the k eff values submitted by the participants, neutron flux distributions were recalculated for each participant. From these distributions, spatial dependent correction factors were obtained. Finally, the neutron flux distributions supplied by the participants were rescaled for the reference k eff value of 0.95 using these spatial dependent correction factors. The rescaled neutron flux distributions are presented in Figures 6, 7 and 8 and refer to the equilibrium core. Figure 6. Axial flux distribution in the target region; results scaled to a k eff value of 0.95 1.6E+16 1.4E+16 Neutron Flux 1.2E+16 1E+16 8E+15 6E+15 ANL CIEMAT KAERI PSI/CEA JAERI RIT (JEF) RIT (ENDF) SCK-CEN 4E+15 2E+15 0 0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 Axial position (cm) 388
Figure 7. Axial flux distribution in the fuel region; results scaled to a k eff value of 0.95 4.5E+15 4E+15 Neutron Flux 3.5E+15 3E+15 2.5E+15 2E+15 ANL CIEMAT KAERI PSI/CEA JAERI RIT (JEF) RIT (ENDF) SCK-CEN 1.5E+15 1E+15 5E+14 0 0 10 20 30 40 50 60 70 80 90 100 110 120 Axial position (cm) 130 140 150 160 170 180 190 200 Figure 8. Radial flux distribution in the mid-plane; results scaled to a k eff value of 0.95 9E+15 8E+15 Neutron Flux 7E+15 6E+15 5E+15 4E+15 ANL CIEMAT KAERI PSI/CEA JAERI RIT (JEF) RIT (ENDF) SCK-CEN 3E+15 2E+15 1E+15 0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 92 100 110 120 130 142 Radial position (cm) In the fuel region, the shape of the axial neutron flux distributions is in good agreement for most participants. However, the peak position reported by KAERI is shifted to the core centre (Z = 100 cm). The spread in the absolute value of the flux is still significant and the difference 389
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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
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
Page 362 and 363: Figure 6. Two-dimensional cluster p
Page 364 and 365: Figure 8. Excitation functions for
Page 366 and 367: REFERENCES [1] D. Ridikas, thesis,
Page 368 and 369: 1. Introduction Since 1991, the Com
Page 370 and 371: Experimental reactivity control tec
Page 372 and 373: Table 2. Neutron intensities Target
Page 374 and 375: experimental channels (horizontal a
Page 376 and 377: 376
Page 378 and 379: Table 3. Planned experimental progr
Page 380 and 381: 1. Introduction and benchmark speci
Page 382 and 383: neutrons. Since the neutron flux is
Page 384 and 385: Figure 2. Microscopic capture cross
Page 386 and 387: Figure 4. k eff variation in the st
Page 390 and 391: etween the highest and the lowest v
Page 392 and 393: The isotope specific β eff values
Page 395: SESSION IV BASIC PHYSICS, MATERIALS
Page 398 and 399: 1. Introduction Due to its excellen
Page 400 and 401: Figure 2. Tests scheme 0 340 h. 1 0
Page 402 and 403: Figure 4. Auger depth profile conce
Page 404 and 405: Figure 8. Auger depth profile conce
Page 406 and 407: deposited at the cold zone, and the
Page 408 and 409: inner layer grows inward from the o
Page 410 and 411: [8] V.M. Fedirko, O.I. Eliseeva, V.
Page 412 and 413: 1. Introduction One of the main par
Page 414 and 415: 3. Tantalum target irradiation The
Page 416 and 417: At 10-MeV neutron irradiation, radi
Page 418 and 419: 1. Introduction HYPER (HYbrid Power
Page 420 and 421: this study, we used an orthogonal c
Page 422 and 423: Figure 5. Temperature distribution
Page 424 and 425: Figure 7. Thermal stress distributi
Page 427 and 428: FUEL/TARGET CONCEPTS FOR TRANSMUTAT
Page 429 and 430: (U 0.55 Pu 0.4 Np 0.05 )O 2 fuels w
Page 431 and 432: Figure 3. Left: Ceramograph of a (Z
Page 433 and 434: Figure 6. Left: ceramograph of a(Zr
Page 435 and 436: AMERICIUM TARGETS IN FAST REACTORS
Page 437 and 438: The reference case for all comparis
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It should be underlined that this c
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Cases Table 3. Heterogeneous recycl
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• A later step could be to add Cm
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RESEARCH ON NITRIDE FUEL AND PYROCH
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temperature for (Cm,Pu)N followed t
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Figure 1. Temperature dependence of
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The difference of two fuel pins exi
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In addition to the voltammetric stu
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2 wt% of Pu at 773 K. For the momen
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[13] M. Akabori, M. Takano, A. Itoh
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1. Introduction For the management
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The scientific feasibility of pluto
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Another option using a basis of sta
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6.2.1 Inert matrices 6.2.1.1 MgAl 2
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eached respectively 38.5% and 70% F
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Figure 4. Experiments for MA transm
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Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
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9.3 Programme for dedicated fuels F
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[14] R.J.M. Konings et al., The EFT
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1. Introduction An accelerator driv
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corresponding Pb-Bi velocity is 1.1
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the fission product target. The rod
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fuel rods are at the TRU assembly t
Page 489:
SESSION V TRANSMUTATION SYSTEMS AND
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1. Introduction Since the 50s, nitr
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A three dimensional model of a sub-
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Figure 4. Change in k-eigenvalue fo
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[4] Y. Arai et al., Experimental Re
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Nomenclature ADS: ATW: GT-MHR: LOF:
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Regarding switching off the beam, o
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Figure 3. Beam blocking 10 min (200
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Figure 7. A possible scenario for n
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[15] Greenspan E. et al., The Encap
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1. Introduction In the EADF design
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Equation (6) can be improved by con
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where L is obtained by a summation
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
Page 526 and 527:
2.2 Representation of MA transmutat
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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
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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
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neutron source, the reactor can mai
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atoms. For fuel region Rf = 2.5 cm,
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Figure 3. Neutron flux spectra for
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
Page 559 and 560:
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
Page 569 and 570:
hexagonal assemblies of 122 mm plat
Page 571 and 572:
to achieve the requested performanc
Page 573 and 574:
3 MYRRHA associated R&D programme F
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collaboration with Forschungszentru
Page 577:
• Industrial partners, in particu
Page 580 and 581:
1. Introduction The transmutation o
Page 582 and 583:
Existing accelerators have been des
Page 584 and 585:
suggested to look for an innovative
Page 586 and 587:
Table 1. Main lead-bismuth eutectic
Page 588 and 589:
4.3 The core The basic fuel sub-ass
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Figure 1. Experimental accelerator
Page 593 and 594:
HELIUM-COOLED REACTOR TECHNOLOGIES
Page 595 and 596:
of its potential use in nuclear wea
Page 597 and 598:
Figure 2. Neutron flux distribution
Page 599 and 600:
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
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1. Introduction The study of the be
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Plutonium was simulated with the no
Page 620 and 621:
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.
Page 626 and 627:
1. Introduction The long-term radio
Page 628 and 629:
Ce Ce 3+ Cl - Cl 2 The voltammogram
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Figure 3. Chronopotentiograms for t
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Figure 4. Potentiometric titrations
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Experimental solubilization tests w
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[13] H. Flood T. Förland and K. Mo
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
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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
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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
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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
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
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
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
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MOLTEN SALTS AS POSSIBLE FUEL FLUID
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2. The fuel salt for MSB concept Ma
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and minor actinides must be removed
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4. Container material studies 4.1 F
Page 849 and 850:
management. The major developments
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
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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
Page 883 and 884:
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
Page 890 and 891:
MEPI within the framework of Projec
Page 893 and 894:
NEW ORIGINAL IDEAS ON ACCELERATOR D
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During conceptual investigations of
Page 897 and 898:
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
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
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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
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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
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1. Introduction The Nuclear Enginee
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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
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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
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1. Background Radiation background
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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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