Search - OECD Nuclear Energy Agency

More documents

Recommendations

Info

potentials that must be maintained to avoid intergranular cracking for nickel-based alloys. Techniques developed under other reactor programs to improve the resistance of stainless steels to helium embrittlement should be extended to include nickel-base alloys. 4.2 Fission product clean up unit The materials required for fission product clean up unit depend of course, upon the nature of the chosen process and upon the design of the equipment to implement the process. For MSB the key operation in the fuel treatment is removal of rare earth, alkali-metal, alkaline-earth fission products from the fuel solvent before its return, along with the TRUs, to the reactor. The crucial process in most of the processing vessels is that liquids be conducted to transfer selected materials from one stream to the another. Such a fission product cleanup unit based on metal transfer process at least will present a variety of corrosive environments, including: • Molten salts and molten alloys containing e.g. bismuth, lithium or other metals at 650°C. • HF-H 2 mixtures and molten fluorides, along with bismuth in some cases, at 550-650°C. • Interstitial impurities on the outside of the system at temperature to 650°C, particularly if graphite and refractory metals are used. Certainly, the R&D on the materials for the fission product clean up unit for MSB is at very early stage. A layer of frozen salt will probably serve to protect surfaces that are worked under oxidising conditions, if the layer can be maintained in the complex equipment. RRC-KI preliminary tests at molten salt loops [11,12] showed that the thickness of the frozen film on the wall was predictable and adhered to the wall. The only materials that are truly resistant to bismuth and molten salts are refractory metals (W, Mo, Ta) [1] and graphite (e.g. graphite with isotropic pyloric coating tested in RRC-KI [12] for both working fluids), neither of which is attractive for fabricating a large and complicated system. Development work to determine if iron base alloys can be protected with refractory metal coatings should probably be considered for higher priority. The approach taken to materials development could be to initially emphasise definition of the basic material capabilities with working fluids and interstitial impurities, and then to develop a knowledge of fabrication capabilities. 5. ISTC supported R&D To solve some of the mentioned in previous sections essential issues, Russian Institutes (RFNC- All-Russian Institute of Technical Physics, (Chelyabinsk-70), RRC-Kurchatov Institute (Moscow), Institute of Chemical Technology (Moscow) and Institute of High Temperature Electrochemistry (Ekaterinburg)) have submitted to the ISTC the Task #1606 Experimental Study of Molten Salt Technology for Safe and Low Waste Treatment of Plutonium and Minor ActinidesiIn Accelerator Driven and Critical Systems. The general purpose of the project is to perform an integral evaluation of potential of the selected molten salt fuel as applied to safe, low-waste and proliferation resistant treatment of radwaste and Pu 848
management. The major developments that will be pursued in the framework of the project are the following: • Experimental study of behaviour and fundamental properties of prospective molten salt compositions. • Experimental verification of candidate structural materials for fuel circuit. • Reactor physics and fuel cycle consideration and recommendations on the key points of MSB concept development. First two objectives are considered as the most crucial to the MSB further development. There are no doubts that the candidate constituents of the solvent system for MSB concept must be LiF, NaF, BeF 2 , maybe with minor additions of some other fluorides in order to provide required fuel properties. In contrast with well-established 2LiF-BeF 2 solvent system, for the other prospective compositions there is essential uncertainty in fundamental data, necessary to estimate their potential for MSB fuelled by plutonium and minor actinides. Some of the salt components required for the experiments are commercially available and will be purchased, but some other salts have to be prepared basing on the technology developed by the participating institutes. Particularly, Pu, Np and Am trifluorides will be prepared at VNIITF site by pyrochemical method of HF gas treatment. Although starting materials of very high purity will be used in production of the fluorides, a careful analysis and, in some cases, a further purification will be needed before the salts usage in cell and loop systems. Two steps of purification would be required: one for the removal of oxides and sulfides and one for the removal of structural metal fluorides (NiF 2 , FeF 2 , CrF 2 , etc.) The measurements of basic properties of prospective molten salt fuels will be carried out by means of techniques, which are mastered or will be developed in the participating institutions. First, it is planned to evaluate a phase diagram for the selected solvent and perform its experimental verification on several points. Also, it is planned to measure molten salt properties, such as actinides/lanthanides solubility, viscosity, thermal conductivity, standard potentials of actinides and rare-earth fluorides and equilibrium distribution coefficients of lanthanides in the two-phase system. Heat capacity, vapour pressure and density of the selected mixture can be calculated with a reasonable accuracy. Measurements of the properties will be carried out in a range of temperatures from 350°C to 800°C. Two main types of candidate structural materials for the MSB primary circuit will be tested. First ones are samples of the Ni-based alloy Hastelloy-N, modified according to the ORNL and RRC-KI recommendations, the second will be prospective stainless steel samples. The corrosion tests will be carried out with selected fuel salt under conditions simulating the design ones with a working temperature up to 700-750°C, fuel salt heat up about 100°C, as well as with additions simulating the main fission products. The tests will be carried out at thermal convection loops with the samples exposure time in a flow till to 1 000 hours. It is planned to develop a technique for redox potential control and monitoring and apply it at the corrosion test loops. After the samples exposition, their detailed examinations will be carried out and corrosion rate will be measured. On the basis of these studies, the conclusion about the candidate structural materials compatibility with the selected salt will be made. The experimental data will be fed into the conceptual design efforts. The objectives of the conceptual studies are to consider a candidate flow-sheet for MSB concept, that would be feasible. 849
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 ........
Page 7 and 8:
EXECUTIVE SUMMARY More than 160 par
Page 9:
identified. In the fuel area, labor
Page 12 and 13:
17:20-19:05 Session III: Partitioni
Page 14 and 15:
Poster sessions Poster session: Par
Page 17 and 18:
WELCOME ADDRESS Lucila Izquierdo Ge
Page 19 and 20:
WELCOME ADDRESS Michel Hugon Co-ord
Page 21 and 22:
WELCOME ADDRESS Philippe Savelli De
Page 23:
developments. This will surely beco
Page 26 and 27:
use of FBRs for transmutation toget
Page 28 and 29:
view, i.e. better use of uranium an
Page 30 and 31:
W. Forsberg proposes to reduce the
Page 32 and 33:
1. From the open fuel cycle to the
Page 34 and 35:
Figures 2 and 3 show the radiotoxic
Page 36 and 37:
Denoting the transuranic (TRU) or m
Page 38 and 39:
or, in terms of the fuel burn-up an
Page 40 and 41:
quantities of LWR-MOX and FR-MOX wi
Page 42 and 43:
view of the historic development, t
Page 44 and 45:
Table 5. Assumptions for transmutat
Page 46 and 47:
separating troublesome fission prod
Page 48 and 49:
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 102 and 103:
Table 2. Values of Dj (neutron cons
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
Page 153 and 154:
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
Page 159 and 160:
The accelerator driven transmutatio
Page 161 and 162:
substantiate this recommendation, s
Page 163 and 164:
current, advanced and innovative nu
Page 165 and 166:
ACCELERATOR DRIVEN SUB-CRITICAL SYS
Page 167 and 168:
demonstration of feasibility of a E
Page 169 and 170:
An extended “skeleton” for ADS
Page 171 and 172:
• Fertile support (uranium) is no
Page 173:
7. Conclusions The TWG under the ch
Page 176 and 177:
1. Introduction The priorities for
Page 178 and 179:
In the EURATOM Fourth Framework Pro
Page 180 and 181:
Table 2. Cluster on transmutation-t
Page 182 and 183:
6. Community research for the perio
Page 184 and 185:
REFERENCES [1] “Council Decision
Page 186 and 187:
1. Introduction Back in 1989, the O
Page 188 and 189:
would need the continuation of tech
Page 190 and 191:
individual isotopes as a function o
Page 192 and 193:
Therefore, while there is continuin
Page 194 and 195:
[9] OECD/NEA, Overview of Physics A
Page 197 and 198:
RECENT TOPICS IN R&D FOR THE OMEGA
Page 199 and 200:
Figure 1. Partitioning and transmut
Page 201 and 202:
The present 4-GPP necessitates a pr
Page 203 and 204:
5. Concluding remarks In 1999, the
Page 205:
REFERENCES [1] T. Mukaiyama, T. Tak
Page 208 and 209:
1. Introduction CIEMAT is actively
Page 210 and 211:
adiotoxicity to be managed could al
Page 212 and 213:
Figure 3. Mass composition of the d
Page 214 and 215:
Figure 6. Fuel cycle assumed in the
Page 216 and 217:
the 4 batches scheme, allowing to a
Page 218 and 219:
Figure 11. Transmutation efficiency
Page 220 and 221:
1. Introduction Spent fuels of mode
Page 222 and 223:
Figure 3. A change in radiotoxicity
Page 224 and 225:
These dependencies are shown on Fig
Page 226 and 227:
When increasing the moderator fract
Page 228 and 229:
Even greater power increases are ob
Page 230 and 231:
The effect of a moderator volume fr
Page 232 and 233:
Table 11. Different isotopes contri
Page 234 and 235:
Thus the transmutation of such FPs
Page 237 and 238:
ASSESSMENT OF NUCLEAR POWER SCENARI
Page 239 and 240:
elease probabilities. The time dist
Page 241 and 242:
Table 2. Annual heavy nuclide contr
Page 243 and 244:
Figure 3. Reduction of potential ra
Page 245 and 246:
DISPOSAL OF PARTITIONING-TRANSMUTAT
Page 247 and 248:
Figure 2. Decay heat from SNF 2000
Page 249 and 250:
Figure 3. Shorter-lived HHR reposit
Page 251 and 252:
4. Management of low-heat, long-liv
Page 253 and 254:
isotope from other caesium isotopes
Page 255 and 256:
THE AMSTER CONCEPT J. Vergnes 1 , D
Page 257 and 258:
Figure 1. Layout diagram of the mol
Page 259 and 260:
Table 1. Definition of configuratio
Page 261 and 262:
We therefore adopted a partial purg
Page 263 and 264:
conceivable. Thus by increasing the
Page 265 and 266:
6. R&D needed to validate the AMSTE
Page 267:
SESSION III PARTITIONING J.P. Glatz
Page 271 and 272:
PARTITIONING-SEPARATION OF METAL IO
Page 273 and 274:
The terpyridyl reagent (ligand L 1
Page 275 and 276:
Figure 2. The synthesis of ADTPTZ a
Page 277 and 278:
2.4 Implications for partitioning T
Page 279 and 280:
SEPARATION OF MINOR ACTINIDES FROM
Page 281 and 282:
installed in a hot cell. The feed w
Page 283 and 284:
the concentrations of U, Pu and Np
Page 285 and 286:
Table 2 shows the recovery in the r
Page 287 and 288:
PARTITIONING ANIONIC AGENTS BASED O
Page 289 and 290:
which of these, the Co 3+ , Fe 3+ a
Page 291 and 292:
This dianionic species must be extr
Page 293 and 294:
Figure 6 Ph 2 P acetone PPh 2 H2 O
Page 295 and 296:
Figure 9 H 3 C RO(CH 2 )n CH 3 (CH
Page 297:
[7] J. Rais and P. Selucky, Nucleon
Page 301 and 302:
PYROCHEMICAL PROCESSING OF IRRADIAT
Page 303 and 304:
The metallic cadmium product of the
Page 305 and 306:
Figure 2. Schematic flow-sheet for
Page 307 and 308:
R&D OF PYROCHEMICAL PARTITIONING IN
Page 309 and 310:
(first of all pumps) for fluoride m
Page 311 and 312:
4. Research on material and equipme
Page 313:
REFERENCES [1] Uhlir J., Pyrochemic
Page 316 and 317:
1. Introduction The increasing inte
Page 318 and 319:
Figure 2. Stainless steel box with
Page 320 and 321:
Figure 4. U deposit on solid cathod
Page 322 and 323:
Figure 7. Schematic flow of the cou
Page 324 and 325:
actinide elements from spent (metal
Page 327 and 328:
DEVELOPMENT OF PLUTONIUM RECOVERY P
Page 329 and 330:
uranium dendrite and that uranium c
Page 331 and 332:
Table 1. Conditions and results of
Page 333 and 334:
Cathode potential went down to -1.6
Page 335 and 336:
Figure 6. Change of LCC potential i
Page 337 and 338:
Figure 9. Relation between Pu conce
Page 339 and 340:
consideration described in the prec
Page 341:
[13] Y. Arai, S. Fukushima, K. Shio
Page 345:
SESSION IV BASIC PHYSICS, MATERIALS
Page 348 and 349:
1. Introduction The reduction of th
Page 350 and 351:
agrees ours within limits of errors
Page 352 and 353:
Figure 1. Thermal neutron capture c
Page 354 and 355:
[18] A.P. Baerg, R.M. Bartholomew,
Page 356 and 357:
1. Introduction Nowadays it is well
Page 358 and 359:
In order to describe the inter-nucl
Page 360 and 361:
kind of measurements allow to chara
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 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
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
Page 439 and 440:
It should be underlined that this c
Page 441 and 442:
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
Page 474 and 475:
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: 4. Container material studies 4.1 F
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
show all

Search - OECD Nuclear Energy Agency

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?