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Table 2. Values of Dj (neutron consumption per fission) for isotopes j or for a fuel type (Dj
Table 2. Values of Dj (neutron consumption per fission) for isotopes j or for a fuel type (Dj
Table 3. Radiotoxicity data (CD = Cancer Dose Hazard) Isotope Toxicity factor CD/Ci Half-life Years Toxicity factor CD/g Actinides and their daughters 210 Pb 455.0 22.3 3.48E4 223 Ra 15.6 0.03 7.99E5 226 Ra 36.3 1.60E3 3.59E1 227 Ac 1185.0 21.8 8.58E4 229 Th 127.3 7.3E3 2.72E1 230 Th 19.1 7.54E4 3.94E-1 231 Pa 372.0 3.28E4 1.76E-1 234 U 7.59 2.46E5 4.71E-2 235 U 7.23 7.04E8 1.56E-5 236 U 7.50 2.34E7 4.85E-4 238 U 6.97 4.47E9 2.34E-6 237 Np 197.2 2.14E6 1.39E-1 238 Pu 246.1 87.7 4.22E3 239 Pu 267.5 2.41E4 1.66E1 240 Pu 267.5 6.56E3 6.08E1 242 Pu 267.5 3.75E5 1.65E0 241 Am 272.9 433 9.36E2 242m Am 267.5 141 2.80E4 243 Am 272.9 7.37E3 5.45E1 242 Cm 6.90 0.45 2.29E4 243 Cm 196.9 29.1 9.96E3 244 Cm 163.0 18.1 1.32E4 245 Cm 284.0 8.5E3 4.88E1 246 Cm 284.0 4.8E3 8.67E1 Short-lived fission products 90 Sr 16.7 29.1 2.28E3 0 Y 0.60 7.3E-3 3.26E5 137 Cs 5.77 30.2 4.99E2 Long-lived fission products 99 Tc 0.17 2.13E5 2.28E-3 129 I 64.8 1.57E7 1.15E-2 93 Zr 0.095 1.5E6 2.44E-4 135 Cs 0.84 2.3E6 9.68E-4 14 C 0.20 5.73E3 8.92E-1 59 Ni 0.08 7.6E4 6.38E-3 63 Ni 0.03 100 1.70E0 126 Sn 1.70 1.0E5 4.83E-2 103
- Page 1 and 2:
Nuclear Development ACTINIDE AND FI
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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
- Page 51 and 52: SESSION III Partitioning Chairs: J.
- Page 53 and 54: OVERVIEW OF THE HYDROMETALLURGICAL
- Page 55 and 56: 2.1.3 Consequences Owing to the fac
- Page 57 and 58: The extraction and separation mecha
- Page 59 and 60: extractant was observed. As a conse
- Page 61 and 62: 2.3.2 Examples of strategies and
- Page 63 and 64: 3. Conclusions and perspectives 3.1
- Page 65 and 66: SESSION IV Basic Physics, Materials
- Page 67 and 68: TRANSMUTATION: A DECADE OF REVIVAL
- Page 69 and 70: 2.1 The IFR concept and the homogen
- Page 71 and 72: 2.3 Dedicated systems Making again
- Page 73 and 74: compound “macro-dispersed” in M
- Page 75 and 76: Figure 3. Sketch of ADS, liquid met
- Page 77 and 78: 3.3.2.1 The MEGAPIE project [40] ME
- Page 79 and 80: 3.3.2.2 The MUSE experiments The MU
- Page 81 and 82: Figure 8. Comparison of the neutron
- Page 83 and 84: Figure 9. Scenarios at equilibrium
- Page 85 and 86: goals in this field. Since once-thr
- Page 87 and 88: • The use of Thorium in PWRs alwa
- Page 89 and 90: • Understanding of the role of AD
- Page 91 and 92: [17] Y. Arai, T. Ogawa, Research on
- Page 93: SESSION V Transmutation Systems and
- Page 96 and 97: 1. Introduction The term ADS compre
- Page 98 and 99: • Safety should be “designed in
- Page 100 and 101: 3. Minor actinide and/or transurani
- Page 104 and 105: Table 4. Delayed neutron fraction I
- Page 106 and 107: Figure 4. η (Neutrons released per
- Page 108 and 109: Table 5. ADS Distinguishing feature
- Page 110 and 111: While a favourable ADS safety featu
- Page 112 and 113: Optimised mixes of MA and Pu can be
- Page 114 and 115: Moreover, the fuel is where neutron
- Page 116 and 117: REFERENCES [1] L. Van den Durpel et
- Page 118 and 119: [19] D.C. Wade and E. Fujita, Trend
- Page 121 and 122: POSTER SESSION Basic Physics: Nucle
- Page 123: To conclude, this poster session in
- Page 126 and 127: Five other papers related to ADS co
- Page 129: SESSION I OVERVIEW OF NATIONAL AND
- Page 132 and 133: 1. Current activities for radioacti
- Page 134 and 135: 3.2 Results to date and analyses of
- Page 136 and 137: 3.2.5.2 JNC JNC is considering the
- Page 138 and 139: 4.6 Short-term increase in radiatio
- Page 140 and 141: Annex 1 R&D scheme for partitioning
- Page 142 and 143: Annex 3 Members of the Advisory Com
- Page 144 and 145: plutonium can be recycled in pressu
- Page 146 and 147: choices and the implementation of m
- Page 148 and 149: 1. Introduction Since the 5th Infor
- Page 150 and 151: strata” approach which would invo
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IAEA ACTIVITIES IN THE AREA OF EMER
- Page 155 and 156:
actually started to do so) because
- Page 157 and 158:
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
- Page 197 and 198:
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
- Page 224 and 225:
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
- Page 243 and 244:
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
- Page 251 and 252:
4. Management of low-heat, long-liv
- Page 253 and 254:
isotope from other caesium isotopes
- Page 255 and 256:
THE AMSTER CONCEPT J. Vergnes 1 , D
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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
- 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
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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
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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
- 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
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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
- Page 309 and 310:
(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
- 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
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In order to describe the inter-nucl
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kind of measurements allow to chara
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Figure 6. Two-dimensional cluster p
- 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
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Experimental reactivity control tec
- Page 372 and 373:
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
- Page 382 and 383:
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
- 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
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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
- Page 406 and 407:
deposited at the cold zone, and the
- Page 408 and 409:
inner layer grows inward from the o
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[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
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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
- Page 443 and 444:
• A later step could be to add Cm
- Page 445 and 446:
RESEARCH ON NITRIDE FUEL AND PYROCH
- Page 447 and 448:
temperature for (Cm,Pu)N followed t
- Page 449 and 450:
Figure 1. Temperature dependence of
- Page 451 and 452:
The difference of two fuel pins exi
- Page 453 and 454:
In addition to the voltammetric stu
- Page 455 and 456:
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
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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
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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
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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
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1. Introduction At present, there a
- Page 826 and 827:
target means a change in k and the
- Page 828 and 829:
Following the normal procedure for
- Page 830 and 831:
Acknowledgements This study has bee
- Page 832 and 833:
1. ADS description A conceptual des
- Page 834 and 835:
Substitution of (9) into (8), and u
- Page 836 and 837:
With the coupling LAHET + MCNP-DSP,
- Page 838 and 839:
Figure 3. Comparison for 1 and 5 pu
- Page 841 and 842:
MOLTEN SALTS AS POSSIBLE FUEL FLUID
- Page 843 and 844:
2. The fuel salt for MSB concept Ma
- Page 845 and 846:
and minor actinides must be removed
- Page 847 and 848:
4. Container material studies 4.1 F
- Page 849 and 850:
management. The major developments
- Page 851:
REFERENCES [1] H.J. MacPherson, Dev
- Page 854 and 855:
1. Introduction The Energy Amplifie
- Page 856 and 857:
Table 1. Main parameters of the EAD
- Page 858 and 859:
Table 5. Neutron balance in the who
- Page 860 and 861:
Table 7. Neutron flux distributions
- Page 862 and 863:
Table 8. Displacement rates DPA/yea
- Page 865 and 866:
DEEP UNDERGROUND TRANSMUTOR (PASSIV
- Page 867 and 868:
passive state. By operating at a hi
- Page 869 and 870:
I have proposed using an accelerato
- Page 871 and 872:
Figure 1. Layout of deep undergroun
- Page 873 and 874:
RADIATION CHARACTERISTICS OF PWR MO
- Page 875 and 876:
Table 1. Radiotoxicity of actinides
- Page 877 and 878:
RADIATION CHARACTERISTICS OF URANIU
- Page 879 and 880:
Table 1. Radiotoxicity of actinides
- Page 881 and 882:
INTERNATIONAL CO-OPERATION ON CREAT
- Page 883 and 884:
an international base to combine ef
- Page 885:
• Second topic: interaction of pr
- Page 888 and 889:
1. Introduction The role of acceler
- Page 890 and 891:
MEPI within the framework of Projec
- Page 893 and 894:
NEW ORIGINAL IDEAS ON ACCELERATOR D
- Page 895 and 896:
During conceptual investigations of
- Page 897 and 898:
delay, interface and computer. The
- Page 899 and 900:
2. Channel-vessel design of ADS bla
- Page 901 and 902:
Table 1. Characteristics of the ful
- Page 903:
[14] Karavaev G.N., Kiselev G.V., M
- Page 906 and 907:
1. Introduction The problem of nucl
- Page 908 and 909:
Table 3. Radiotoxicity in americium
- Page 910 and 911:
Table 5. Characteristics of station
- Page 912 and 913:
1. Introduction The atomic power en
- Page 914 and 915:
of lead-bismuth target are given in
- Page 917 and 918:
CRITICAL AND SUB-CRITICAL GT-MHRs F
- Page 919 and 920:
Table 1. Basic GT-MHR reactor param
- Page 921 and 922:
Figure 2. Typical change of the ave
- Page 923 and 924:
Scenario S4. This case is actually
- Page 925 and 926:
Figure 3. A change in radiotoxicity
- Page 927:
[13] P. Goberis, Modelling of Innov
- Page 930 and 931:
1. Introduction The Nuclear Enginee
- Page 932 and 933:
Some simplifications have been made
- Page 934 and 935:
Figure 3. Velocity vectors Some of
- Page 936 and 937:
Figure 6. Temperature evolution at
- Page 938 and 939:
• Two main reasons can explain th
- Page 940 and 941:
1. Introduction Actually, we notice
- Page 942 and 943:
This problem can be solved by using
- Page 944 and 945:
The evaluations obtained in [2] hav
- Page 946 and 947:
REFERENCES [1] Management and Dispo
- Page 948 and 949:
1. Background Radiation background
- Page 950 and 951:
the long-term hazard of spent fuel,
- Page 952 and 953:
In a transmutation fuel cycle inclu
- Page 954 and 955:
Figure 4. Potential biological haza
- Page 956 and 957:
cooling prior to SF reprocessing an
- Page 958:
REFERENCES [1] White Book of Nuclea
- Page 961 and 962:
ORDER FORM OECD Nuclear Energy Agen
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