Scenario with inert matrix fuel: a specific study

被引：1
|
作者：
Doriath, JY [1 ]
Grouiller, JP [1 ]
Pavageau, J [1 ]
de Saint-Jean, C [1 ]
机构：
[1] CEA Cadarache, DRN, DER, SPRC, F-13108 St Paul Durance, France
来源：
PROGRESS IN NUCLEAR ENERGY | 2001年 / 38卷 / 3-4期
关键词：
strategy studies; innovation; plutonium; minor actinide management;
D O I：
10.1016/S0149-1970(00)00149-9
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
In this paper, we describe a strategy study concerning the future of the French nuclear energy infrastructure, with a scenario involving reactors loaded with inert matrix fuel. We select the problem of the inventory control of minor actinides by target introduction into fast reactors. Added to pressurized water reactors in the French nuclear infrastructure, this scenario permits one to balance plutonium and minor actinide production and consumption and to obtain a substantial reduction of the radiological impact compared to a non-reprocessing fuel scenario on a one million year scale. (C) 2001 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码：419 / 422
页数：4
相关论文
共 50 条
  • [41] The behaviour under irradiation of molybdenum matrix for inert matrix fuel containing americium oxide (CerMet concept)
    D'Agata, E.
    Knol, S.
    Fedorov, A. V.
    Fernandez, A.
    Somers, J.
    Klaassen, F.
    JOURNAL OF NUCLEAR MATERIALS, 2015, 465 : 820 - 834
  • [42] The irradiation test of Inert-Matrix Fuel in comparison to uranium plutonium mixed oxide fuel at the Halden Reactor
    Kasemeyer, U
    Hellwig, C
    Lee, YW
    Ledergerber, G
    Sohn, DS
    Gates, GA
    Wiesenack, W
    PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) : 309 - 312
  • [43] Synthesis and characterization of zirconia-magnesia inert matrix fuel: Uranium homolog studies
    Holliday, Kiel
    Hartmann, Thomas
    Poineau, Frederic
    Kennedy, J. Rory
    Czerwinski, Ken
    JOURNAL OF NUCLEAR MATERIALS, 2009, 393 (02) : 224 - 229
  • [44] Material attractiveness evaluation of inert matrix fuel for nuclear security and non-proliferation
    Aoki, Takeshi
    Sagara, Hiroshi
    Han, Chi Young
    ANNALS OF NUCLEAR ENERGY, 2019, 126 : 427 - 433
  • [45] Transmutation of actinides in inert-matrix fuels: fabrication studies and modelling of fuel behaviour
    Konings, RJM
    Bakker, K
    Boshoven, JG
    Hein, H
    Huntelaar, ME
    van der Laan, RR
    JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) : 84 - 90
  • [46] Sintering behaviour and microstructures of carbides and nitrides for the inert matrix fuel by spark plasma sintering
    Ryu, Ho Jin
    Lee, Young Woo
    Cha, Seung Il
    Hong, Soon Hyung
    JOURNAL OF NUCLEAR MATERIALS, 2006, 352 (1-3) : 341 - 348
  • [47] Thoria based inert matrix fuel production via sol-gel process
    Ozdemir, I.
    Yayli, A.
    Ozbek, I.
    PROGRESS IN NUCLEAR ENERGY, 2016, 86 : 63 - 70
  • [48] Fabrication of particle dispersed inert matrix fuel based on liquid phase sintered SiC
    Pavlyuchkov, D.
    Baney, R. H.
    Tulenko, J. S.
    Seifert, H. J.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (02) : 139 - 146
  • [49] Behaviour of implanted xenon in yttria-stabilised zirconia as inert matrix of a nuclear fuel
    Degueldre, C
    Pouchon, M
    Döbeli, M
    Sickafus, K
    Hojou, K
    Ledergerber, G
    Abolhassani-Dadras, S
    JOURNAL OF NUCLEAR MATERIALS, 2001, 289 (1-2) : 115 - 121
  • [50] Synthesis and characterization of zirconia-magnesia inert matrix fuel: Ce homolog studies
    Holliday, Kiel
    Hartmann, Thomas
    Czerwinski, Ken
    JOURNAL OF NUCLEAR MATERIALS, 2009, 392 (03) : 487 - 493
12345