对事故后一些物理现象下的堆外中间量程测量通道IRC(Intermediate Range Channel)的响应进行了分析,包括停堆后(N-1)组控制棒组件下落、反应堆水池淹没、堆芯空泡份额或堆芯裸露等。分析发现,事故工况下IRC的响应并不一定反映堆芯次临...对事故后一些物理现象下的堆外中间量程测量通道IRC(Intermediate Range Channel)的响应进行了分析,包括停堆后(N-1)组控制棒组件下落、反应堆水池淹没、堆芯空泡份额或堆芯裸露等。分析发现,事故工况下IRC的响应并不一定反映堆芯次临界度的变化。从状态导向事故运行程序SOP(State Oriented Procedure)堆芯次临界度监测的目的出发,对SOP中堆芯次临界度监测阈值的选取和一回路状态功能监测优先级的确定给出了建议。展开更多
High-level waste is an important safety issue in the development of nuclear power.A proposed solution is the transmutation of waste in fast reactors.The exclusion of the risk of supercriticality by using subcritical r...High-level waste is an important safety issue in the development of nuclear power.A proposed solution is the transmutation of waste in fast reactors.The exclusion of the risk of supercriticality by using subcritical reactors is currently under development.Controlling the subcriticality level in such reactors presents difficulties.A problem is posed by the so-called space effect observed when using in reactors many neutron detectors in different locations of the core and reflector.Reactivity obtained from measure-ments,for example,by the Sjo¨strand method,differs by nonnegligible values.Numerical corrections can partially improve this situation.The use of a monoisotopic fission chamber set,designed for a given reactor,when each chamber is intended for a specific position in the system,can improve the situation.A question arises about the sensitivity of the results to reactivity changes.This issue is analyzed by computer simulation for possible fissionable and fissile nuclides for the total range of control rod insertion,changes in reactor fuel enrichment,and fuel temperature.The tested sensitivity was satisfactory at most levels from several dozen to several hundred pcm.A case study was conducted using the VENUS-F core model.展开更多
文摘对事故后一些物理现象下的堆外中间量程测量通道IRC(Intermediate Range Channel)的响应进行了分析,包括停堆后(N-1)组控制棒组件下落、反应堆水池淹没、堆芯空泡份额或堆芯裸露等。分析发现,事故工况下IRC的响应并不一定反映堆芯次临界度的变化。从状态导向事故运行程序SOP(State Oriented Procedure)堆芯次临界度监测的目的出发,对SOP中堆芯次临界度监测阈值的选取和一回路状态功能监测优先级的确定给出了建议。
基金This research was supported by the Polish Ministry of Science and Higher Education,and in part by the PL Grid Infrastructure available at Academic Computer Center CYFRONET AGH.APC was funded by the AGH-University of Science and Technology,Cracow,Poland.
文摘High-level waste is an important safety issue in the development of nuclear power.A proposed solution is the transmutation of waste in fast reactors.The exclusion of the risk of supercriticality by using subcritical reactors is currently under development.Controlling the subcriticality level in such reactors presents difficulties.A problem is posed by the so-called space effect observed when using in reactors many neutron detectors in different locations of the core and reflector.Reactivity obtained from measure-ments,for example,by the Sjo¨strand method,differs by nonnegligible values.Numerical corrections can partially improve this situation.The use of a monoisotopic fission chamber set,designed for a given reactor,when each chamber is intended for a specific position in the system,can improve the situation.A question arises about the sensitivity of the results to reactivity changes.This issue is analyzed by computer simulation for possible fissionable and fissile nuclides for the total range of control rod insertion,changes in reactor fuel enrichment,and fuel temperature.The tested sensitivity was satisfactory at most levels from several dozen to several hundred pcm.A case study was conducted using the VENUS-F core model.
