Discrete element method for simulation of early-life thermal fracturing behavior in ceramic nuclear fuel pellets

被引:43
作者
Huang, Hai [1 ]
Spencer, Benjamin [1 ]
Hales, Jason [1 ]
机构
[1] Idaho Natl Lab, Idaho Falls, ID 83401 USA
关键词
MECHANICAL-BEHAVIOR; UO2; CRACKING; MODEL; MICROSTRUCTURE; STRENGTH;
D O I
10.1016/j.nucengdes.2014.05.049
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
A discrete element method (DEM) representation of coupled solid mechanics, fracturing and heat conduction processes is developed and applied to explicitly simulate the random initiation and subsequent propagation of interacting thermal cracks in a ceramic nuclear fuel pellet during initial rise to power and during power cycles. The DEM model clearly predicts realistic early-life crack patterns including both radial and circumferential cracks. Simulation results clearly demonstrate the formation of radial cracks during the initial power rise and formation of circumferential cracks as the power is ramped down. In these simulations, additional early-life power cycles do not lead to the formation of new thermal cracks. They do, however clearly indicate changes in the apertures of thermal cracks during later power cycles due to thermal expansion and shrinkage. The number of radial cracks increases with increasing power, which is consistent with the experimental observations. Published by Elsevier B.V.
引用
收藏
页码:515 / 528
页数:14
相关论文
共 43 条
[1]  
Allison C.M., 1993, Tech. Rep. NUREG/CR-6150, EGG-2720
[2]  
[Anonymous], 1989, HERON
[3]   THERMAL-SHOCK CRACK PATTERNS EXPLAINED BY SINGLE AND MULTIPLE CRACK-PROPAGATION [J].
BAHR, HA ;
FISCHER, G ;
WEISS, HJ .
JOURNAL OF MATERIALS SCIENCE, 1986, 21 (08) :2716-2720
[4]   MULTIPLE CRACK-PROPAGATION IN A STRIP CAUSED BY THERMAL-SHOCK [J].
BAHR, HA ;
WEISS, HJ ;
MASCHKE, HG ;
MEISSNER, F .
THEORETICAL AND APPLIED FRACTURE MECHANICS, 1988, 10 (03) :219-226
[5]   HEAT-TRANSFER IN LMFBR FUEL-ELEMENTS .2. EFFECTS OF FUEL PELLET CRACKS, GRANULAR FUEL STRUCTURE AND AZIMUTHALLY NONUNIFORM HEAT-TRANSFER FROM CLADDING TO BULK COOLANT [J].
BARRETT, PR .
NUCLEAR ENGINEERING AND DESIGN, 1974, 26 (03) :388-403
[6]   MECHANICAL-BEHAVIOR MODELING OF FRACTURED NUCLEAR-FUEL PELLETS [J].
BERNAUDAT, C .
NUCLEAR ENGINEERING AND DESIGN, 1995, 156 (03) :373-381
[7]  
Bolander J.E., 2005, PHYS REV B, V71, P12
[8]   Fracture analyses using spring networks with random geometry [J].
Bolander, JE ;
Saito, S .
ENGINEERING FRACTURE MECHANICS, 1998, 61 (5-6) :569-591
[9]  
BUESCHER BJ, 1974, AM CERAM SOC BULL, V53, P621
[10]   DEFORMATION OF UO2 AT HIGH TEMPERATURES [J].
CANON, RF ;
ROBERTS, JTA ;
BEALS, RJ .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1971, 54 (02) :105-&