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采用ANC-H程序分析堆芯燃耗,采用ORIGENS程序计算乏燃料组件的核素成分、中子发射率和中子发射能谱,采用MCNP程序建立田湾核电站堆芯、堆外结构和探测器布置中子输运模型(图1),计算不同堆芯装、换料模式下堆外源量程探测器的响应,分析以堆外源量程探测器取代换料监测设备监督堆芯中子通量密度变化的可能性。
The nuclear burnup was analyzed by ANC-H program, and the nuclear component, neutron emission and neutron emission energy of the spent fuel assembly were calculated by ORIGENS program. The MCNP program was used to establish the core, stack structure and detector of Tianwan nuclear power plant The neutron transport model (Fig. 1) is arranged to calculate the response of the reactor with different core loading and refueling modes. The reactor external heuristic detector is used to replace the refueling monitoring equipment to monitor the reactor core neutron flux The possibility of density changes.