A combined thermal and strength analysis of the behavior of a VVER-440 reactor's vessel during an accident involving core melting

被引：4
|
作者：
Rassokhin N.G. [1 ]
Loktionov V.D. [1 ]
Mukhtarov E.S. [1 ]
机构：
[1] Moscow Power Institute, Moscow, 111250
来源：
Thermal Engineering | 2006年 / 53卷 / 9期
关键词：
Thermal Load; Reactor Vessel; Gage Pressure; Creep Model; Reactor Pressure Vessel;
D O I：
10.1134/S0040601506090023
中图分类号：
学科分类号：
摘要：
Results from parametric calculations of the thermal and strength behavior of a VVER-440 reactor's vessel during a beyond-design-basis accident are presented. The ranges of gage pressure inside the vessel and the conditions of externally cooling the reactor with water are presented under which the corium that appears in the reactor vessel during a severe accident can be held there for a long time. © Nauka/Interperiodica 2006.
引用
收藏
页码：675 / 681
页数：6
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