Some Experimental Work Performed on the BOR-60 Reactor

被引：0
|
作者：
G. I. Gadzhiev
V. N. Efimov
I. Yu. Zhemkov
A. S. Korol'kov
V. I. Polyakov
Yu. E. Shtynda
Yu. L. Revyakin
机构：
[1] State Science Center of the Russian Federation – Scientific-Research Institute of Nuclear Reactors,
来源：
Atomic Energy | 2001年 / 91卷
关键词：
Radionuclide; Fuel Element; Fuel Assembly; Steam Generator; Radiation Parameter;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The experimental work performed on a BOR-60 reactor over a period of 30 years of reactor operation is briefly reviewed. The results of investigations of the neutron-physical, thermohydraulic, and dynamical characteristics and the safety parameters of the reactor are presented. The investigations performed and the analysis of transient and emergency regimes made it possible to improve the standard shutdown and cooldown systems in order to soften the temperature conditions on the reactor components.
引用
收藏
页码：913 / 922
页数：9
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