中国实验快堆技术规格书审评中重点关注问题探讨  

Discussion on Key Issues in the Review of Technical Specifications for China Experimental Fast Reactor

作　　者：李珊珊 和丹 LI Shan-shan;HE Dan(China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China)

机构地区：[1]中国核电工程有限公司,北京100840

出　　处：《中国核电》2022年第1期32-34,44,共4页China Nuclear Power

摘　　要：快堆是我国核电三步走战略中的关键一环,也是第四代核能系统中的主力堆型。中国实验快堆是我国第一座快堆,其中对技术规格书的审查尤其重视。技术规格书是核设施运行期间的“法律”,它规定了核设施在正常运行、瞬态和异常工况下,遵照的技术参数和技术要求,主要包括安全限值、保护阈值、运行限制条件以及监督要求。本文主要阐述了中国实验快堆在技术规格书审查过程中,审评依据、审评过程以及关注的重点问题进行探讨,对重点问题提出了建议。Fast reactor is a key step in China’s three-step nuclear power development strategy, and also the main reactor type in the fourth generation nuclear power system. China Experimental Fast Reactor(CEFR) is the first fast reactor in China. The technical specification is the “law” during the operation of nuclear facilities, which specifies the technical parameters and requirements of nuclear facilities under normal, transient and abnormal operation conditions, mainly including the safety limit, protection threshold, operation limit and supervision requirement. In this paper, the basis, process and key issues of technical specification review for China Experimental Fast Reactor(CEFR) are discussed, and some suggestions are put forward.

关 键 词：快堆 核安全审评 探讨 技术规格书 

分 类 号：TL490[核科学技术—核技术及应用]