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METHOD AND ITS CORRESPONDING APPARATUS OF VERIFICATION AND ONLINE ANALYSIS OF INTEGRITY AGAINST NON-DUCTILE FAILURE OF THE PRESSURE CONTAINER WALL OF A NUCLEAR REACTOR.
METHOD AND ITS CORRESPONDING APPARATUS OF VERIFICATION AND ONLINE ANALYSIS OF INTEGRITY AGAINST NON-DUCTILE FAILURE OF THE PRESSURE CONTAINER WALL OF A NUCLEAR REACTOR.
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机译:核反应堆压力容器壁非延性破坏的完整性验证和在线分析方法及其相应装置
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摘要
A real time monitoring and analysis of nuclear reactor vessel integrity is performed by monitoring reactor coolant temperature and pressure and fast neutron fluence, and generating therefrom a visual comparison of the reference nil-ductility transition temperature, RTndt, required for flaw initiation and the actual RTndt through the entire depth of the vessel wall at selected critical points. The thermocouples disposed at the reactor core inlet and the resistance temperature detectors, RTDs, disposed at the cold leg conduits provide a measurement of the coolant temperature at the critical points of the vessel. Under stagnant flow conditions, empirically developed conversion factors are applied to the RTD and thermocouple readings to provide the best estimate of the coolant temperature at the critical points.
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