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Figure 3. XY loading (at the core mid-plane) of the MUSE-4 reference critical configuration (provisional) Figure 4. Neutron pulse time spectrum 0.2 0.175 Ionic Current particles 0.15 Arbitrary Unit 0.125 0.1 0.075 0.05 0.025 0 1000 800 600 400 200 0 200 400 600 800 1000 Time (ns) 377
Page 1 and 2:
Nuclear Development ACTINIDE AND FI
Page 3 and 4:
FOREWORD The objective of the OECD/
Page 5 and 6:
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
Page 205:
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
Page 228 and 229:
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
Page 313:
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
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
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 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 388 and 389: 2.4 Neutron flux distribution One r
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
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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
Page 439 and 440:
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
Page 445 and 446:
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
Page 466 and 467:
6.2.1 Inert matrices 6.2.1.1 MgAl 2
Page 468 and 469:
eached respectively 38.5% and 70% F
Page 470 and 471:
Figure 4. Experiments for MA transm
Page 472 and 473:
Figure 5a. Ecrix B rig Figure 5b. E
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A CEA/Minatom work programme is und
Page 476 and 477:
9.3 Programme for dedicated fuels F
Page 478 and 479:
[14] R.J.M. Konings et al., The EFT
Page 480 and 481:
1. Introduction An accelerator driv
Page 482 and 483:
corresponding Pb-Bi velocity is 1.1
Page 484 and 485:
the fission product target. The rod
Page 486 and 487:
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-
Page 496 and 497:
Figure 4. Change in k-eigenvalue fo
Page 498 and 499:
[4] Y. Arai et al., Experimental Re
Page 500 and 501:
Nomenclature ADS: ATW: GT-MHR: LOF:
Page 502 and 503:
Regarding switching off the beam, o
Page 504 and 505:
Figure 3. Beam blocking 10 min (200
Page 506 and 507:
Figure 7. A possible scenario for n
Page 508 and 509:
[15] Greenspan E. et al., The Encap
Page 510 and 511:
1. Introduction In the EADF design
Page 512 and 513:
Equation (6) can be improved by con
Page 514 and 515:
where L is obtained by a summation
Page 516 and 517:
Figure 1. The natural convection im
Page 518 and 519:
Figure 4 shows the temperature tren
Page 520 and 521:
[12] P.H. Wakker, Thermal Hydraulic
Page 522 and 523:
1. Introduction Research and develo
Page 524 and 525:
Table 2. Core design parameters for
Page 526 and 527:
2.2 Representation of MA transmutat
Page 528 and 529:
Figure 1(b) shows the cases for the
Page 530 and 531:
It is found that the higher MA tran
Page 532 and 533:
REFERENCES [1] T. Ikegami, H. Hayas
Page 534 and 535:
1. Introduction The management of t
Page 536 and 537:
Table 1. Core performance of MA and
Page 538 and 539:
Figure 3. Nuclear electricity capac
Page 540 and 541:
Table 3. Experimental items at PEF
Page 542 and 543:
REFERENCES [1] Takano H., Akie H.,
Page 544 and 545:
1. Introduction and background The
Page 546 and 547:
neutron source, the reactor can mai
Page 548 and 549:
atoms. For fuel region Rf = 2.5 cm,
Page 550 and 551:
Figure 3. Neutron flux spectra for
Page 552 and 553:
A possible way to maintain the k ef
Page 554 and 555:
higher than 99% of 239 Pu, and high
Page 557 and 558:
TRANSMUTATION OF NUCLEAR WASTES WIT
Page 559 and 560:
Figure 1. PBT conceptual view Table
Page 561 and 562:
very tight holders for fission frag
Page 563 and 564:
5. Cooling system A preliminary des
Page 565 and 566:
spectral densities [10,11] and can
Page 567 and 568:
MYRRHA, A MULTI-PURPOSE ADS FOR R&D
Page 569 and 570:
hexagonal assemblies of 122 mm plat
Page 571 and 572:
to achieve the requested performanc
Page 573 and 574:
3 MYRRHA associated R&D programme F
Page 575 and 576:
collaboration with Forschungszentru
Page 577:
• Industrial partners, in particu
Page 580 and 581:
1. Introduction The transmutation o
Page 582 and 583:
Existing accelerators have been des
Page 584 and 585:
suggested to look for an innovative
Page 586 and 587:
Table 1. Main lead-bismuth eutectic
Page 588 and 589:
4.3 The core The basic fuel sub-ass
Page 590 and 591:
Figure 1. Experimental accelerator
Page 593 and 594:
HELIUM-COOLED REACTOR TECHNOLOGIES
Page 595 and 596:
of its potential use in nuclear wea
Page 597 and 598:
Figure 2. Neutron flux distribution
Page 599 and 600:
atio. Given this rate of destructio
Page 601 and 602:
Figure 5. Irradiated TRISO particle
Page 603 and 604:
in ceramic-coated microspheres of t
Page 605 and 606:
(LOCA) event. The effect on this fe
Page 607 and 608:
Figure 13. Elevation AD-FMHR The fa
Page 609:
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
Page 673 and 674:
RECENT PROGRESSES ON PARTITIONING S
Page 675 and 676:
hot tests (See Table2) was enough f
Page 677 and 678:
trace amount of Am and Eu. The HBTM
Page 679 and 680:
6. Conclusion Declassification of t
Page 681:
POSTER SESSION BASIC PHYSICS: NUCLE
Page 684 and 685:
1. Introduction Among the large num
Page 686 and 687:
The simulation of the spallation pr
Page 688 and 689:
Table 1. Parameters of the two coll
Page 690 and 691:
Figure 4. Radial distribution of th
Page 692 and 693:
6. The neutron escape line The comm
Page 694 and 695:
Figure 7. Neutron background at the
Page 697 and 698:
RECENT CAPTURE CROSS-SECTIONS VALID
Page 699 and 700:
Figure 1. The GENEPI accelerator an
Page 701 and 702:
2.3.3 Neutron flux measurements •
Page 703 and 704:
Figure 6. Time spectrum of 3 He gas
Page 705 and 706:
4. Analysis 4.1 Background subtract
Page 707 and 708:
Figure 11. ENDF/B-VI, JEF2.2 and JE
Page 709 and 710:
DOUBLE DIFFERENTIAL CROSS-SECTION F
Page 711 and 712:
3. Conclusion Double differential c
Page 713 and 714:
Figure 3. Preliminary results of do
Page 715 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
Page 841 and 842:
MOLTEN SALTS AS POSSIBLE FUEL FLUID
Page 843 and 844:
2. The fuel salt for MSB concept Ma
Page 845 and 846:
and minor actinides must be removed
Page 847 and 848:
4. Container material studies 4.1 F
Page 849 and 850:
management. The major developments
Page 851:
REFERENCES [1] H.J. MacPherson, Dev
Page 854 and 855:
1. Introduction The Energy Amplifie
Page 856 and 857:
Table 1. Main parameters of the EAD
Page 858 and 859:
Table 5. Neutron balance in the who
Page 860 and 861:
Table 7. Neutron flux distributions
Page 862 and 863:
Table 8. Displacement rates DPA/yea
Page 865 and 866:
DEEP UNDERGROUND TRANSMUTOR (PASSIV
Page 867 and 868:
passive state. By operating at a hi
Page 869 and 870:
I have proposed using an accelerato
Page 871 and 872:
Figure 1. Layout of deep undergroun
Page 873 and 874:
RADIATION CHARACTERISTICS OF PWR MO
Page 875 and 876:
Table 1. Radiotoxicity of actinides
Page 877 and 878:
RADIATION CHARACTERISTICS OF URANIU
Page 879 and 880:
Table 1. Radiotoxicity of actinides
Page 881 and 882:
INTERNATIONAL CO-OPERATION ON CREAT
Page 883 and 884:
an international base to combine ef
Page 885:
• Second topic: interaction of pr
Page 888 and 889:
1. Introduction The role of acceler
Page 890 and 891:
MEPI within the framework of Projec
Page 893 and 894:
NEW ORIGINAL IDEAS ON ACCELERATOR D
Page 895 and 896:
During conceptual investigations of
Page 897 and 898:
delay, interface and computer. The
Page 899 and 900:
2. Channel-vessel design of ADS bla
Page 901 and 902:
Table 1. Characteristics of the ful
Page 903:
[14] Karavaev G.N., Kiselev G.V., M
Page 906 and 907:
1. Introduction The problem of nucl
Page 908 and 909:
Table 3. Radiotoxicity in americium
Page 910 and 911:
Table 5. Characteristics of station
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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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