首页> 美国政府科技报告 >A SURVEY OF THERMAL AND MECHANICAL ASPECTS OF SOME H.T.G.C. REACTOR CORE DESIGNS UTILISING BERYLLIUM OXIDE MODERATION
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A SURVEY OF THERMAL AND MECHANICAL ASPECTS OF SOME H.T.G.C. REACTOR CORE DESIGNS UTILISING BERYLLIUM OXIDE MODERATION

机译:某些H.T.G.C.的热力学和机械学方面的调查反应堆核心设计利用氧化铍调节

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摘要

This report presents results of a study, from July 1962, to June 1963, by the Core Development Group (Engineering Research Division), of various reactor core configurations for a high temperature gas cooled reactor system, using fuels dispersed in unclad BeO with BeO moderation and CO2 gas coolant. The configurations are naturally classified into two groups:one, Parallel Channel Reactors (cores with fixed internal geometry and specific coolant channels), and the other, Pebble Bed Reactors.nThe major advantages and design problems of each type are discussed. Methods for solution of the problems are suggested. Although the reactor types are compared, it is impossible to recommend any one type in preference to the others, owing to the lack of reliable nuclear and cost data.

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