CORE COOLABILITY OF AN ATR BY HEAVY-WATER MODERATOR IN SITUATIONS BEYOND DESIGN BASIS ACCIDENTS

被引:12
|
作者
MOCHIZUKI, H
KOIKE, MH
SAKAI, T
机构
[1] Power Reactor and Nuclear Fuel Development Corporation, O-arai Engineering Center, Ibaraki-ken, 311-13, 4002 Narita, O-arai
关键词
D O I
10.1016/0029-5493(93)90145-Y
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
In the case of a loss-of-coolant accident (LOCA) with coincident loss of emergency coolant injection (LOECI), core cooling is generally very severe. However, as the ATR plant has heavy water at about 60-degrees-C in the core, decay heat can be removed by the heavy water cooling system. Separate-effects tests relating to heavy water cooling were conducted with each setup. The important thermal hydraulics was radiation heat transfer, ballooning of a pressure tube, contact conductance between the pressure tube and a calandria tube and critical heat flux of the calandria tube. Constants and correlations obtained by the tests were incorporated into several codes to assess the core cooling. Long term core cooling capability with the heavy water cooling system was assessed. The core was cooled without melting under the postulated events due to inherent characteristics of the ATR.
引用
收藏
页码:293 / 303
页数:11
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