EXPERIMENTAL STUDY OF A PASSIVE SYSTEM FOR LOWERING DAMAGING PRESSURE LEVELS IN THE PROTECTIVE SHELL OF THE KLT-40S REACTOR FACILITY

被引：4

作者：

Bakhmetiev, A. M. ^{[1
]}

Bolshukhin, M. A. ^{[1
]}

Khizbullin, A. M. ^{[1
]}

Kamnev, M. A. ^{[1
]}

机构：

[1] Afrikantov Expt Design Bur Mech Engn, Nizhnii Novgorod, Russia

来源：

ATOMIC ENERGY | 2010年 / 108卷 / 05期

基金：

俄罗斯基础研究基金会;

关键词：

Natural Circulation; Reactor Facility; Protective Shell; Cool Loop; Secondary Loop;

D O I：

10.1007/s10512-010-9299-7

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 designs of the new-generation reactor facilities, including floating nuclear heat and electricity plants, new passive containment safety systems are used to increase operational safety. The objective of the present work is to validate experimentally the effectiveness of heat removal by a system which lowers damaging pressure levels in the protective shell under conditions of the maximum anticipated accident with loss of coolant in the first loop. The results of the experimental studies on a full-scale model of a secondary loop of the first cooling loop for lowering damaging pressure confirm the validity of the technical decisions made; all prescribed design characteristics of the cooling loop are upheld.

引用

页码：343 / 348

页数：6