首页> 外文会议>ASME Pressure Vessels amp;amp;amp; Piping Conference >ASSESSMENT OF STRUCTURAL INTEGRITY ON IRRADIATED STEEL STRUCTURE: FOCUSING ON LONG COLUMN TYPE REACTOR PRESSURE VESSEL SUPPORTS
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ASSESSMENT OF STRUCTURAL INTEGRITY ON IRRADIATED STEEL STRUCTURE: FOCUSING ON LONG COLUMN TYPE REACTOR PRESSURE VESSEL SUPPORTS

机译:辐照钢结构结构完整性评估:专注于长柱式反应器压力容器支架

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The structural steel in a nuclear facility experiences significant degradation due to the accumulated neutron irradiation. Particularly, the long-column type reactor pressure vessel supports have been focused since they resist considerable loading to maintain the primary coolant system in their position and experience high neutron irradiation in low temperature, which is an unfavorable condition for the fracture toughness. This study implemented the API 579-1/ASME FFS-1, fitness-for-service (FFS) method to consider both irradiated mechanical properties and multiple loading cases. A three-dimensional(3D) finite element model of long column type reactor pressure vessel support was built for the linear analysis. The metallurgical properties of reactor pressure vessel support for assessment were estimated by empirical equations. This study provides the structural margin of long-column type reactor pressure vessel support by levels of the loads and levels of the neutron fluence.
机译:核设施中的结构钢因累积中子辐射而产生显着的降解。特别地,长柱式反应器压力容器支撑件被聚焦,因为它们抵抗了相当大的装载以使主冷却剂系统保持在其位置,并且在低温下经历高中的中子辐射,这是骨折韧性的不利条件。本研究实施了API 579-1 / ASME FFS-1,适用性 - 服务(FFS)方法,以考虑辐照的机械性能和多重装载案例。为线性分析构建了长柱式电抗器压力容器支撑件的三维(3D)有限元模型。通过经验方程估算反应器压力容器支撑件的冶金性能。该研究提供了长柱式反应器压力容器支撑的结构裕度,通过中子流量的载荷和水平的水平。

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