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Seismic evaluation of containment shell - WWER-1000 type reactor building

机译:安全壳的抗震评估-WWER-1000型反应堆厂房

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This investigation is part of the Modernization Program for units 5/6 (VVER 1000) of Kozloduy NPP, Bulgaria. ThernReactor Building is studied for the recently defined Review Level Earthquake (RLE) and Local Earthquakes (LE). A 3-DrnFinite Element model is used for definition of seismic response and seismic capacity assessment. Most attention is paid to therncontainment evaluation. For that purpose a complementary finite element model is developed. It represents the cylinder shell,rnthe dome and the supporting ring structure of the containment. The model is characterized by refined mesh and detailedrnrepresentation of loading caused by the stressing tendons. The structural stiffness increase due to prestressing is considered inrnthe modal analysis. First static analysis is performed with the pre-stressing loads, consequently eigenvalue analysis is donernunder consideration of the strains due to prestressing.rnThe capacity check of the containment is performed in meridian and circumferential direction separately. Principlernstresses from several load combinations are examined in order to determine the scenarios for containment cracking and lossrnof integrity. The domination loading is that caused by LOCA. The tension stresses however do not affect the structuralrnintegrity. The seismic effects are of minor importance. The HCLPF values of several scenarios studied show very highrnacceleration that may cause failure.
机译:这项调查是保加利亚Kozloduy NPP 5/6机组(VVER 1000)现代化计划的一部分。对ThernReactor建筑物进行了研究,以用于最近定义的“检查级地震”(RLE)和“局部地震”(LE)。 3-Drn有限元模型用于定义地震响应和评估地震能力。最关注的是包装评估。为此,建立了互补的有限元模型。它代表了安全壳的圆柱壳,穹顶和支撑环结构。该模型的特点是网格细化和应力筋引起的载荷的详细表示。在模态分析中考虑了由于预应力引起的结构刚度增加。首先对预应力进行静态分析,因此,在考虑因预应力引起的应变的情况下进行特征值分析。rn安全壳的容量检查分别在子午线和周向进行。为了确定安全壳破裂和损失完整性的方案,检查了几种载荷组合的主应力。主导负载是由LOCA引起的。然而,张应力不影响结构完整性。地震影响次要。研究的几种方案的HCLPF值显示出很高的加速度,可能会导致故障。

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