Rock-like oxide fuels and their burning in LWRs

被引:26
作者
Yamashita, T [1 ]
Kuramoto, K
Akie, H
Nakano, Y
Nitani, N
Nakamura, T
Kusagaya, K
Ohmichi, T
机构
[1] Japan Atom Energy Res Inst, Dept Nucl Energy Syst, Tokai, Ibaraki 3191195, Japan
[2] Japan Atom Energy Res Inst, Res Org Informat Sci & Technol, Tokai, Ibaraki 3191195, Japan
关键词
ROX fuels; excess plutonium; inert matrix; yttria stabilized zirconia; spinel; irradiation test; threshold enthalpy; reactivity initiated accident; burning;
D O I
10.3327/jnst.39.865
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
Research on the plutonium rock-like oxide (ROX) fuels and their once-through burning in light water reactors has been performed to establish an option for utilizing and disposing effectively the excess plutonium. The ROX fuel is a sort of the inert matrix fuels and consists of mineral-like compounds such as yttria stabilized zirconia, spinel and corundum. A particle-dispersed fuel was devised to reduce damage by heavy fission fragments. Some preliminary results on swelling, fractional gas release and microstructure change for five ROX fuels were obtained from the irradiation test and successive post-irradiation examinations. Inherent disadvantages of the Pu-ROX fuel cores could be improved by adding U-238 or Th-232 as resonant materials, and all improved cores showed a nearly the same characteristics as the conventional UO2 core during transient conditions. The threshold enthalpy of the ROX fuel rod failure was found to be comparable to the fresh UO2 rod by pulse-irradiation tests simulating reactivity initiated accident conditions.
引用
收藏
页码:865 / 871
页数:7
相关论文
共 33 条
[1]   A NEW FUEL MATERIAL FOR ONCE-THROUGH WEAPONS PLUTONIUM BURNING [J].
AKIE, H ;
MUROMURA, T ;
TAKANO, H ;
MATSUURA, S .
NUCLEAR TECHNOLOGY, 1994, 107 (02) :182-192
[2]   An overview of reactivity initiated accident behavior of rock-like fueled pressurized water reactors [J].
Akie, H ;
Nakamura, T .
PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) :363-370
[3]   Core design study on rock-like oxide fuel light water reactor and improvements of core characteristics [J].
Akie, H ;
Takano, H ;
Anoda, Y .
JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) :139-145
[4]   Fission-gas release in a spinel-based fuel used for actinide transmutation [J].
Bakker, K ;
Belvroy, R ;
van den Berg, FA ;
Casalta, S ;
Conrad, R ;
Neeft, EAC ;
Schram, RPC ;
Tams, W .
PROGRESS IN NUCLEAR ENERGY, 2001, 38 (3-4) :313-316
[5]  
BERMAN RM, 1960, J NUCL MATER, V2, P129
[6]   Optimisation of inert matrix fuel concepts for americium transmutation [J].
Chauvin, N ;
Konings, RJM ;
Matzke, H .
JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (1-2) :105-111
[7]   NEUTRON-IRRADIATION DAMAGE IN MGO, AL2O3 AND MGAL2O4 CERAMICS [J].
CLINARD, FW ;
HURLEY, GF ;
HOBBS, LW .
JOURNAL OF NUCLEAR MATERIALS, 1982, 108 (1-2) :655-670
[8]  
CLINARD FW, 1981, CONF811237
[9]   Ion irradiation and annealing effects in Al2O3 and MgAl2O4 [J].
Furuno, S ;
Sasajima, N ;
Hojou, K ;
Izui, K ;
Otsu, H ;
Muromura, T ;
Matsui, T .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 1997, 127 :181-185
[10]  
HARGMAN DL, 1981, MATPRO VER 11