Probability Modeling Taking into Account Nonlinear Processes of a Deformation and Fracture for the Equipment of Nuclear Power Plants

N. Makhutov, M. Gadenin, Igor Alexandrovich Razumovskiy, S. V. Maslov, Dmitriy Olegovich Reznikov
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引用次数: 3

Abstract

At the solution of integrated tasks of strength, safe life and service safety maintenance for the nuclear power plants (NPP) equipment with slow reactors — water-moderated power reactors (WMPR) of VVER type and channel-type graphite-moderated power reactors (GMPR) of RBMK type arise necessity of physical and mathematical modeling of nonlinear processes of a deformation, fracture and damage at nonlinear probability statement. First of all, it concerns deriving determined, statistical and probabilistic characteristics of mechanical properties of reactor materials. Expectations and variation factors of mechanical properties ’ characteristics obtained from experimental researches are inducted into the equations for the verification calculations at determination of static and cyclic strength margins with the use of nominal and local stresses and strains. For the improved determined and probability analysis of these margins modeling experimental researches of stress-strain states of the analyzed equipment are conducted. Special attention at such tests is given to concentration factors and variation factors of loading conditions. The final stage of estimation of basic normative and verification calculation accuracy at laboratory, modeling and test bench researches are full-scale pre-operational tests (cold-hot running-in) of pilot nuclear reactors with the use of the experimental mechanics methods. The conditions of safety service of the NPP equipment are estimated taking into account factors of reaching limiting states by criteria of risk of initiation of emergency situations.
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考虑核电厂设备变形和断裂非线性过程的概率建模
在解决核电厂慢堆设备强度、安全寿命和使用安全维护的综合任务——VVER型水慢堆(WMPR)和RBMK型通道型石墨慢堆(GMPR)的问题时,需要对变形、断裂和损伤的非线性过程进行非线性概率模型的物理和数学建模。首先,它涉及推导反应堆材料力学性能的确定、统计和概率特征。利用名义应力和局部应变,将实验研究所得的力学性能特征期望值和变化因子引入到确定静强度和循环强度裕度时的验证计算方程中。为了改进这些边界建模的确定和概率分析,对被分析设备的应力-应变状态进行了实验研究。在这类试验中,应特别注意荷载条件的集中因素和变化因素。利用实验力学方法对中试核反应堆进行全尺寸运行前试验(冷-热磨合),是实验室、建模和台架研究基本规范估算和验证计算精度的最后阶段。根据启动紧急情况的风险标准,考虑达到极限状态的因素,对核电站设备的安全使用条件进行了估计。
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