ASTEC adaptation for PHWR limited core damage accident analysis

被引:9
|
作者
Majumdar, P. [1 ]
Chatterjee, B. [1 ]
Lele, H. G. [1 ]
Guillard, G. [2 ]
Fichot, F. [2 ]
机构
[1] Bhabha Atom Res Ctr, Reactor Safety Div, Bombay 400085, Maharashtra, India
[2] Inst Radioprotect & Surete Nucl, PSN RES SAG, F-13115 Cadarache, St Paul Lez Dur, France
关键词
NB PRESSURE TUBES; THERMAL-ANALYSIS; TEMPERATURE;
D O I
10.1016/j.nucengdes.2013.10.011
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
Under limited core damage accidents (LCDAs) of Pressurized Heavy Water Reactor (PHWR), coolable geometry of the channel might be retained thanks to the presence of moderator heat sink. Indeed, the pressure tube is amenable to creep deformation at high temperature due to internal pressure and fuel bundles weight. Partial or complete circumferential contact between pressure tube and calandria tube aids heat dissipation to the moderator. A new module has been developed by Bhabha Atomic Research Centre (BARC) for simulating this phenomenon which is specific to horizontal-type of reactors. It requires additional calculation of pressure tube sagging/ballooning and temperature field in the circumferential direction. The module is well validated with available experimental results concerning pressure tube deformation and the associated heat transfer in the area of contact. It is then used in analysing typical LCDAs scenarios in Indian PHWR under low and medium internal pressure conditions. This module is implemented in the ASTEC IRSN-GRS severe accident code version under development and will thus be available in the next major version V2.1. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:273 / 286
页数:14
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