Reliability analysis of dispersion nuclear fuel elements

被引:27
作者
Ding, Shurong [1 ]
Jiang, Xin [1 ]
Huo, Yongzhong [1 ]
Li, Lin an [2 ]
机构
[1] Fudan Univ, Dept Mech & Engn Sci, Shanghai 200433, Peoples R China
[2] Tianjin Univ, Dept Mech, Tianjin 300072, Peoples R China
基金
中国国家自然科学基金; 上海市自然科学基金;
关键词
D O I
10.1016/j.jnucmat.2007.10.006
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Taking a dispersion fuel element as a special particle composite, the representative volume element is chosen to act as the research object. The fuel swelling is simulated through temperature increase. The large strain elastoplastic analysis is carried out for the mechanical behaviors using FEM. The results indicate that the fission swelling is simulated successfully; the thickness increments grow linearly with burnup; with increasing of burnup: (1) the first principal stresses at fuel particles change from tensile ones to compression ones, (2) the maximum Mises stresses at the particles transfer from the centers of fuel particles to the location close to the interfaces between the matrix and the particles, their values increase with burnup; the maximum Mises stresses at the matrix exist in the middle location between the two particles near the mid-plane along the length (or width) direction, and the maximum plastic strains are also at the above region. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:453 / 460
页数:8
相关论文
共 23 条
[1]  
[Anonymous], 1967, DISPERSION FUEL ELEM
[2]   FACTORS AFFECTING SWELLING OF NUCLEAR FUELS AT HIGH-TEMPERATURES [J].
CHUBB, W ;
STORHOK, VW ;
KELLER, DL .
NUCLEAR TECHNOLOGY, 1973, 18 (03) :231-256
[3]  
DUYN LV, 2003, THESIS
[4]  
FISHER EF, 1954, PHYS REV, pA482
[5]   Computational evaluation of effective material properties of composites reinforced by randomly distributed spherical particles [J].
Kari, Sreedhar ;
Berger, Harald ;
Rodriguez-Ramos, Reinaldo ;
Gabbert, Ulrich .
COMPOSITE STRUCTURES, 2007, 77 (02) :223-231
[6]   High burnup fuel behavior related to fission gas effects under reactivity initiated accidents (RIA) conditions [J].
Lemoine, F .
JOURNAL OF NUCLEAR MATERIALS, 1997, 248 :238-248
[7]   A pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: Review and recommendations [J].
Lucuta, PG ;
Matzke, H ;
Hastings, IJ .
JOURNAL OF NUCLEAR MATERIALS, 1996, 232 (2-3) :166-180
[8]  
*MATPRO09, 1976, HDB MAT PROP US ANAL
[9]  
NAKAJIMA T, 1985, FEMAXI111 A COMPUTER
[10]  
NEET EAC, 2003, J NUCL MATER, V317, P217