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RELAP5/MOD3.2 INVESTIGATION OF A WER-1000 MCP SWITCHING ON PROBLEM

机译:RELAP5 / MOD3.2对WER-1000 MCP开关问题的调查

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This paper provides a discussion of various RELAP5 parameters calculated for the investigation of the nuclear power reactor parameter behavior in case of switching on one main coolant pump (MCP) when the other three MCPs are in operation. The reference power plant for this analysis is Unit 6 at the Kozloduy Nuclear Power Plant (NPP) site. Operational data from Kozloduy NPP have been used for the purpose of assessing how the RELAP5 model compares against plant data. During the plant-commissioning phase at Kozloduy NPP Unit 6 a number of experiments have been performed. One of them is switching on MCP when the other three MCPs are in operation. The event is characterized by rapid increase in the flow through the core resulting in a coolant temperature decrease, which leads to insertion of positive reactivity due to the modeled feedback mechanisms. This investigation has been conducted by Bulgarian and Russian specialists on the stage when the reactor power was at 75% of the nominal level. The purpose of the experiment was the complete testing of reliability of all power plant equipment, testing the reliability of the main regulators and defining a jump of the neutron reactor power in case of switching on of one main coolant pump. The Institute for Nuclear Research and Nuclear Energy -Bulgarian Academy of Sciences (INRNE-BAS), Sofia, and Kozloduy NPP have been developing a RELAP5/MOD3.2 model for Kozloduy NPP VVER-1000 for investigation of operational occurrences, abnormal events, and design basis scenarios. This investigation is a process that compares the analytical results obtained by the RELAP5 computer model of the VVER-1000 against the experimental transient data received from the Kozloduy NPP Unit 6. The comparisons between the RELAP5 results and the test data indicate good agreement. This report was possible through the participation of leading specialists from Kozloduy NPP and with the support of Argonne National Laboratory, under the International Nuclear Safety Program (INSP) of the United States Department of Energy.
机译:本文讨论了为研究核动力反应堆参数行为而计算出的各种RELAP5参数,当其他三个MCP处于运行状态时打开一个主冷却剂泵(MCP)时,将对此进行研究。此分析的参考电厂是科兹洛杜伊核电厂(NPP)站点的6号机组。来自Kozloduy NPP的运营数据已用于评估RELAP5模型与工厂数据的比较方式。在Kozloduy NPP 6号机组的试运行阶段,已经进行了许多实验。其中之一是在其他三个MCP运行时打开MCP。该事件的特征是流经堆芯的流量迅速增加,导致冷却剂温度降低,由于建模的反馈机制,导致插入正反应性。这项研究是由保加利亚和俄罗斯的专家在反应堆功率达到标称功率的75%的阶段进行的。实验的目的是对所有电厂设备的可靠性进行全面测试,测试主调节器的可靠性,并确定在打开一个主冷却剂泵的情况下中子反应堆功率的变化。保加利亚科学院核研究与核能研究所(INRNE-BAS),索非亚和Kozloduy NPP一直在为Kozloduy NPP VVER-1000开发RELAP5 / MOD3.2模型,用于调查运行事件,异常事件和设计基础方案。该调查是一个过程,将VVER-1000的RELAP5计算机模型获得的分析结果与从Kozloduy NPP装置6接收到的实验瞬态数据进行了比较。RELAP5结果与测试数据之间的比较表明一致性良好。在美国能源部国际核安全计划(INSP)的支持下,来自Kozloduy NPP的领先专家的参与以及在Argonne国家实验室的支持下,该报告才得以实现。

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