期刊文献+
共找到2篇文章
< 1 >
每页显示 20 50 100
Study of Accident Progression in Unsealed WWER-1000/V320 Reactor during Maintenance
1
作者 Pavlin Groudev Marina Andreeva 《Journal of Power and Energy Engineering》 2016年第8期68-78,共11页
This paper discusses the results obtained during an investigation of WWER-1000 Nuclear Power Plant (NPP) behavior at shutdown reactor during maintenance. For the purpose of the analysis is selected a plant operating s... This paper discusses the results obtained during an investigation of WWER-1000 Nuclear Power Plant (NPP) behavior at shutdown reactor during maintenance. For the purpose of the analysis is selected a plant operating state with unsealed primary circuit by removing the MCP head. The reference nuclear power plant is Unit 6 at Kozloduy NPP (KNPP) site. RELAP5/ MOD3.2 computer code has been used to simulate the transient for WWER-1000/V320 NPP model. A model of WWER-1000 based on Unit 6 of KNPP has been developed for the RELAP5/MOD3.2 code at the Institute for Nuclear Research and Nuclear Energy-Bulgarian Academy of Sciences (INRNE-BAS), Sofia. The plant modifications performed in frame of modernization program have been taken into account for the investigated conditions for the unsealed primary circuit. The most specific in this analysis compared to the analyses of NPP accidents at full power is the unavailability of some important safety systems. For the purpose of the present investigation two scenarios have been studied, involving a different number of safety systems with and without operator actions. The selected initiating event and scenarios are used in support of analytical validation of Emergency Operating Procedures (EOP) at low power and they are based on the suggestions of leading KNPP experts and are important in support of analytical validation of EOP at low power. 展开更多
关键词 Nuclear Power Plant Safety RELAP5/MOD3.2 Computer Code Unsealed wwer type reactor Residual Heat Removal System Low Power and Cold Conditions
下载PDF
基于RELWWER程序的WWER型核电厂燃料棒破损分析 被引量:2
2
作者 杨德锋 肖小祥 +1 位作者 张晔 徐敏 《核安全》 2017年第3期62-67,共6页
裂变产物是一回路冷却剂中放射性核素的重要组成部分,在压水堆核电厂的运行过程中,需对一回路冷却剂进行放射性测量,并根据其中的裂变产物活度监控燃料组件的运行状态。本文通过对比分析RELWWER程序的计算结果和WWER型核电厂一回路冷却... 裂变产物是一回路冷却剂中放射性核素的重要组成部分,在压水堆核电厂的运行过程中,需对一回路冷却剂进行放射性测量,并根据其中的裂变产物活度监控燃料组件的运行状态。本文通过对比分析RELWWER程序的计算结果和WWER型核电厂一回路冷却剂裂变产物比活度的实测数据,给出了初步判断堆芯中燃料棒的破损情况的方法,可为停堆换料方案的制定提供参考。 展开更多
关键词 wwer反应堆 RELwwer程序 实测数据 燃料棒破损
下载PDF
上一页 1 下一页 到第
使用帮助 返回顶部