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Preliminary Stability Evaluation for Core subassembly of Liquid Metal Cooled Fast Reactor with Vertical Seismic Exciting

机译:垂直地震激励液态金属冷却快堆堆芯组件的初步稳定性评估

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Liquid Metal Cooled Fast Reactor (LMFR) is an advanced type of nuclear reactor where the primary coolant is liquid metal. Two typical LMFR, Sodium cooled Fast Reactor (SFR) and Lead cooled Fast Reactor (LFR) are selected as the prior scheme of the GEN IV nuclear power system due to its inherent safety features and economic features. Common configuration of LMFR is designed as pool type, and fuel assembly is supported by core support structure at the footing. The fuel assembly is weak constrained in the vertical direction to reserve the space for refuelling, either pressured on the roof or fixed on the upper header. Reactor safety under seismic exciting is design basis, especially for core subassembly. In this paper preliminary stability evaluation for fuel assembly of LMFR with vertical seismic exciting is performed, taking typical SFR and LFR configuration into consideration. The behaviour of fuel assembly with free-standing under vertical seismic loading was discovered and investigated via analytical method. With relationship between siding term and resistance term, the analytical formulation is constructed in non-dimensional form. The typical reactors were taken for examples, the results show that SFR has lower requirement for core subassembly density than LFR, and may be impossible to simplify the seismic requirement for LFR with free standing design, which will provide a certain theoretical support for seismic design of LFR core assembly.
机译:液态金属冷却快堆(LMFR)是一种先进的核反应堆,其主要冷却剂是液态金属。由于其固有的安全性和经济性,选择了两种典型的LMFR,钠冷快堆(SFR)和铅冷快堆(LFR)作为GEN IV核电系统的现有方案。 LMFR的通用配置设计为池式,燃料组件由位于底部的核心支撑结构支撑。燃料组件在垂直方向上受约束很弱,以保留加油的空间,该空间可以压在车顶上或固定在上集管上。地震激励下的反应堆安全性是设计基础,特别是对于铁心组件。在本文中,考虑了典型的SFR和LFR配置,对带有垂直地震激励的LMFR燃料组件进行了初步的稳定性评估。通过分析方法发现并研究了立式燃料组件在垂直地震作用下的行为。借助侧倾项和抵抗项之间的关系,分析公式以无量纲形式构建。以典型反应堆为例,结果表明,SFR对铁心组件密度的要求比LFR低,可能无法通过独立设计来简化LFR的抗震要求,这将为硅钢的抗震设计提供一定的理论支持。 LFR核心组件。

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