Thermal analysis of severe channel damage caused by a stagnation channel break in a PHWR

被引：17

作者：

Mukhopadhyay, D ^{[1
]}

Majumdar, P ^{[1
]}

Behera, G ^{[1
]}

Gupta, SK ^{[1
]}

Raj, VV ^{[1
]}

机构：

[1] Bhabha Atom Res Ctr, Hlth Safety & Environm Grp, Reactor Safety Div, Bombay 400085, Maharashtra, India

来源：

JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME | 2002年 / 124卷 / 02期

关键词：

stagnation channel breaks; rapid temperature rise in fuel; severe fuel damage; melting and LOCA;

D O I：

10.1115/1.1463036

中图分类号：

TH [机械、仪表工业];

学科分类号：

0802 ;

摘要：

The reactor channel of the horizontal core of pressurized heavy water reactors experiences very low sustained flow during loss of coolant accident (LOCA) at the reactor inlet,feeders caused by certain breaks known as critical channel breaks. 117 this type of accident the reactor trip is delayed causing a gross mismatch of the heat generation and heat removal in the channel, thus leading to rapid temperature rise in the affected channel. A study has been carried out to identify the phenomena and the break size leading to such a situation. Severe fuel damage is predicted in the channel.

引用

页码：161 / 167

页数：7