An investigation of the survivability of fuel-rod claddings during the first stage of the maximum design basis accident at a nuclear power station with a VVER reactor

被引：0

作者：

Karetnikov G.V. ^{[1
]}

Bezrukov Yu.A. ^{[1
]}

Bogdanov A.S. ^{[1
]}

Trushin A.M. ^{[1
]}

Onshin V.P. ^{[1
]}

Smirnov A.V. ^{[1
]}

机构：

[1] Gidropress Experimental Design Office Federal State Unitary Enterprise (OKB Gidropress), Podol'sk, Moscow Oblast, 142103

来源：

Thermal Engineering | 2006年 / 53卷 / 1期

关键词：

Standard Condition; Maximum Rate; Pressure Difference; Transport Phenomenon; Design Basis;

D O I：

10.1134/S0040601506010046

中图分类号：

学科分类号：

摘要：

The survivability of single tubular cpecimens of fuel-rod claddings made of E110 and E635 alloys is experimentally investigated in the range of maximum temperature peaks 760-1450°C and pressure differences of 1-12 MPa across the cladding under conditions of the maximum rates of heating (61-227 K/s) and cooling (6-276 K/s) typical of the first stage of the maximum design basis accident at an nuclear power station with a VVER reactor. The extent to which the experimental conditions simulate the standard conditions is analyzed. © Nauka/Interperiodica 2006.

引用

页码：19 / 25

页数：6