Recrystallization and fission-gas-bubble swelling of U-Mo fuel

被引:71
作者
Kim, Yeon Soo [1 ]
Hofman, G. L. [1 ]
Cheon, J. S. [2 ]
机构
[1] Argonne Natl Lab, Argonne, IL 60439 USA
[2] Korea Atom Energy Res Inst, Taejon 305353, South Korea
关键词
IRRADIATION-INDUCED RECRYSTALLIZATION; BURNUP UO2 FUEL; DISPERSION FUEL; NUCLEAR-FUELS; MICROSTRUCTURE; BEHAVIOR; PELLETS; MODEL;
D O I
10.1016/j.jnucmat.2013.01.291
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
At high burnup, U-Mo fuel exhibits some form of recrystallization, by which fuel grains are subdivided. The effect of grain subdivision is to effectively enhance fission gas bubble (FGB) swelling due to increased grain boundaries. Inter-granular FGB swelling, i.e., FGB formation and growth at the grain boundaries, is much larger than the intra-granular FGB swelling. Recrystallized fuel volume fractions of U-Mo fuels irradiated to fission densities reaching 5.7 x 10(21) f/cm(3) were measured. Analytical expressions of recrystallization kinetics of U-Mo fuel during irradiation have been developed through the usage of the Avrami equation, a phenomenological equation which is also used to describe similar typical transformation reactions, such as new phase formation. In this work, we present a novel FGB swelling model of U-Mo fuel that is expressed in terms of Mo content, extent of cold work (fuel powder fabrication method), and fission density. (c) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:14 / 22
页数:9
相关论文
共 26 条
[1]  
[Anonymous], 2012, COMMUNICATION
[2]  
[Anonymous], 2008, ANL-08/11
[3]   Kinetics of phase change I - General theory [J].
Avrami, M .
JOURNAL OF CHEMICAL PHYSICS, 1939, 7 (12) :1103-1112
[4]   FISSION FRAGMENT DISTRIBUTION IN IRRADIATED UO2 [J].
BERMAN, RM .
NUCLEAR SCIENCE AND ENGINEERING, 1963, 16 (03) :315-&
[5]   DEVELOPMENT AND CHARACTERISTICS OF THE RIM REGION IN HIGH BURNUP UO2 FUEL PELLETS [J].
CUNNINGHAM, ME ;
FRESHLEY, MD ;
LANNING, DD .
JOURNAL OF NUCLEAR MATERIALS, 1992, 188 :19-27
[6]  
DeHoff R., 1968, QUANTITATIVE MICROSC
[7]   Transmission electron microscopy characterization of irradiated U-7Mo/Al-2Si dispersion fuel [J].
Gan, J. ;
Keiser, D. D., Jr. ;
Wachs, D. M. ;
Robinson, A. B. ;
Miller, B. D. ;
Allen, T. R. .
JOURNAL OF NUCLEAR MATERIALS, 2010, 396 (2-3) :234-239
[8]  
Hofman Gerard Leonard, 2005, Nuclear Engineering and Technology, V37, P299
[9]   IRRADIATION ENHANCED CREEP IN LMFBR FUEL-ELEMENT CLADDING [J].
HOFMAN, GL ;
TRUFFERT, J ;
DUPOUY, JM .
JOURNAL OF NUCLEAR MATERIALS, 1977, 65 (01) :200-203
[10]   MICROSCOPIC INVESTIGATION INTO THE IRRADIATION BEHAVIOR OF U3O8-AL DISPERSION FUEL [J].
HOFMAN, GL ;
COPELAND, GL ;
SANECKI, JE .
NUCLEAR TECHNOLOGY, 1986, 72 (03) :338-344