Nuclear fuel rod simulators development for researching the PWR accidental thermohydraulic processes

被引：0
|
作者：
Balashov, S.M.
Kumskoj, V.V.
Pavlov, A.M.
Ulanovskij, A.A.
机构：
来源：
Atomnaya Energiya | 1992年 / 73卷 / 06期
关键词：
Cooling systems - Heat transfer - Hydraulics - Loss of coolant accidents - Nuclear fuel cladding - Nuclear fuel elements - Nuclear fuels - Nuclear reactor accidents - Reactor cores - Reactor operation - Temperature distribution;
D O I：
暂无
中图分类号：
TL4 [各种核反应堆、核电厂];
学科分类号：
082703 ;
摘要：
Designs of fuel rod simulators developed for solving the problems characteristic of nuclear accidents with coolant loss are considered. The simulators indicated high electrical and thermal characteristics. High accuracy of modeling thermal characteristics of fuel elements is achieved. Method for cable pair termination under simulator shell is proposed. The fuel rod simulators are characterized by simple design, availability of structural materials. reliability of operation under high temperature conditions and possibility of their serial production for various type reactors.
引用
收藏
页码：470 / 474
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