The integral thermal-hydraulic test facility is an important part of the design certification and
safety review of nuclear power plants. During the past few decades, a considerable number …

Several passive safety systems are included in the design of the Economic Simplified
Boiling Water Reactor (ESBWR) safety system. To investigate the capability of the ESBWR …

Abstract The RELAP5/MOD3. 3 code was used to simulate a Main Steam Line Break (MSLB)
Loss of Coolant Accident (LOCA) on a Generation III type Reactor with passive safety …

PUMA-E is an integral test facility, which is used for extensive experimental investigations to
study the behavior of Boiling Water Reactor (BWR) plants under accident conditions. The …

The effects of an elevation angle and heat fluxes of a lower tube on saturated pool boiling
heat transfer of tandem tubes were investigated experimentally. For the test, two smooth …

Abstract A generation III+ Boiling Water Reactor (BWR) which relies on natural circulation
has evolved from earlier BWR designs by incorporating passive safety features to improve …

A safety evaluation of SMART adopting a fully passive safety system was performed for a
small-break loss of coolant accident (SBLOCA) with various break locations and sizes using …

摘要核电厂安全壳过滤排放系统是严重事故的重要缓解措施之一, 能够通过过滤, 排气, 降压,
防止安全壳发生超压失效. 目前, 许多国家已重启或开启了对安全壳过滤排放系统的研究工作 …

In this work, the possibility of contamination of environment by radioactive elements due to a
steam-line break accident has been investigated for a VVER-1200 type nuclear power plant …

Abstract A postulated Large Break Loss-Of-Coolant-Accident (LB LOCA) on a generic
Generation III+ Boiling Water Reactor (BWR) equipped with passive safety systems has …