Fracture mechanical evaluation of an in-vessel melt retention scenario

被引:6
作者
Abendroth, M. [1 ]
Willschuetz, H. G. [1 ]
Altstadt, E. [1 ]
机构
[1] Forschungszentrum, D-01328 Dresden, Germany
关键词
D O I
10.1016/j.anucene.2007.08.007
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
This paper presents methods to compute J-integral values for cracks in two- and three-dimensional thermo-mechanical loaded structures using the finite element code ANSYS. The developed methods are used to evaluate the behavior of a crack on the outside of an emergency cooled reactor pressure vessel (RPV) during a severe core melt down accident. It will be shown, that water cooling of the outer surface of a RPV during a core melt down accident can prevent vessel failure due to creep and ductile rupture. Further oil, we present J-integral values for an assumed crack at the outside of the lower plenum of the RPV, at its most stressed location for all emergency cooling (thermal shock) scenario. (C) 2007. Elsevier Ltd. All rights reserved.
引用
收藏
页码:627 / 635
页数:9
相关论文
共 17 条
[1]  
AMESTOY N, 1987, MECH RES COMMUN, V8, P231
[2]  
BASS B, 1983, INT J FRACTURE, V104, pR3
[3]   APPLICATIONS OF ENERGY-RELEASE RATE TECHNIQUES TO PART-THROUGH CRACKS IN EXPERIMENTAL PRESSURE-VESSELS [J].
BASS, BR ;
BRYAN, RH ;
BRYSON, JW ;
MERKLE, JG .
JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1982, 104 (04) :308-316
[4]  
BECHTA SV, 2006, P ICAPP 06 REN NV US
[5]  
Brocks W., 2001, GKSSWMS0108
[6]  
Bui V.A., 1998, THESIS ROYAL I TECHN
[7]   Turbulence modelling for large volumetrically heated liquid pools [J].
Dinh, TN ;
Nourgaliev, RR .
NUCLEAR ENGINEERING AND DESIGN, 1997, 169 (1-3) :131-150
[8]  
Hellen T. K., 1975, International Journal for Numerical Methods in Engineering, V9, P187, DOI 10.1002/nme.1620090114
[9]  
NUKIJAMA S, 1934, JAPANESE SOC MECH EN, V36, P367
[10]  
REMPE J, 1994, NUCL SAFETY, V35, P313