| 对中国实验快堆(CEFR)某些系统和设备核安全分级的探讨 |
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| 引用本文： | 徐及明.对中国实验快堆(CEFR)某些系统和设备核安全分级的探讨[J].核科学与工程,1999(4). |
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| 作者姓名： | 徐及明 |
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| 作者单位： | 北京核工程研究设计院!100840 |
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| 摘 要： | 简要叙述了先进堆型模块式高温气冷堆(MHTGR)、先进沸水堆(ABWR)和中国实验快堆(CEFR)的良好安全特性并给出了它们某些系统和设备安全级别与现行压水堆PWR和沸水堆BWR的比较。据此，并通过对CEFR三回路、通风系统和柴油发电机组等安全功能的分析，从而对它们的安全分级提出了建议。
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| 关 键 词： | 先进堆 安全特性 安全级别 非核级 |
EXPLORATION ON SAFETY CLASSIFICATION OFSOME SYSTEMS AND COMPONENTS FOR CEFR |
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| XU Jiming.EXPLORATION ON SAFETY CLASSIFICATION OFSOME SYSTEMS AND COMPONENTS FOR CEFR[J].Chinese Journal of Nuclear Science and Engineering,1999(4). |
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| Authors: | XU Jiming |
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| Abstract: | The good safety characteristics of advanced reactors MHTGR. ABWR and China Exp erimental Fast Reactor (CEFR) are briefly describeed in Comparison of safety clas sification of some systems and components for MHTGR and ABWR with the present P WR and BWR. Based on the analyses of safety functions for the third circuit, rentilation system and diesel generation set etc. of CEFR, a safety classification is proposed for these systems and components. |
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| Keywords: | advanced reactor safety characteristics safety classifi cation non-nuclear class |
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