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Investigations of the Thermohydraulic Characteristics of Models of Reactor Fuel Assemblies at Kurchatov Atomic Energy Institute.

机译：对库尔恰托夫原子能研究所反应堆燃料组件模型的热液压特性的研究。

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For abstract,see NSA 32 03,number 08020.

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作者
osmachkin, v. s.;
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年度 1975
页码 1-36
总页数 36
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
bwr type reactors; fuel assemblies; pwr type reactors; fuel assemblies; fuel assemblies; critical heat fluxfluid flow; heat transfer; mockup; simulation; testing;

机译：bwr型反应堆;燃料组件; pwr型反应堆;燃料组件;燃料组件;临界热流体流动;传热;模型;模拟;测试;

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Investigations of the Thermohydraulic Characteristics of Models of Reactor Fuel Assemblies at Kurchatov Atomic Energy Institute.

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