Assessment of Structural Integrity on Irradiated Steel Structure: Focusing on Long Column Type Reactor Pressure Vessel Supports

Goeun Han, S. Guzey
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Abstract

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.
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辐照钢结构结构完整性评价——以长柱式反应堆压力容器支架为例
核设施的钢结构由于累积的中子辐照而发生明显的退化。特别是长柱式反应堆压力容器支架,由于其承受相当大的载荷以维持一次冷却剂系统在其位置上,并且在低温下经历高中子辐照,这对断裂韧性不利,因此受到关注。本研究采用API 579-1/ASME FFS-1,即适用性(FFS)方法来考虑辐照力学性能和多种载荷情况。建立了长柱式反应堆压力容器支架的三维有限元模型,进行了线性分析。用经验方程估计了评价用反应堆压力容器支架的冶金性能。通过载荷水平和中子通量水平,给出了支撑长柱式反应堆压力容器的结构裕度。
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