【作者】 姚垚； 邓程程； 杨军；

【Author】 YAO yao;DENG Cheng-cheng;YANG Jun;Department of Nuclear Engineering and Technology , School of Energy and Power Engineering, Huazhong University of Science and Technology;

【机构】 华中科技大学能源与动力工程学院核工程与核技术系；

【摘要】 第三代的非能动先进压水反应堆例如AP1000采用了非能动安全系统,在常规余热排出系统失效时可通过非能动安全系统排出堆芯余热以保障反应堆安全。APEX(Advanced Plant Experiment)台架是以AP1000为原型的整体性试验台架,为AP1000的安全系统设计和长期冷却能力的验证提供支持。本文使用最佳估算程序RELAP5/MOD3.3对APEX台架进行分析建模,并参照特定小破口失水事故(SBLOCA)实验条件设定初始和边界条件。在运行事故瞬态的基础上对反应堆主回路系统和非能动堆芯冷却系统中的主要设备中的关键物理现象——主回路系统行为以及堆芯补水箱(CMT)、安注箱(ACC)、安全壳内置换料水箱(IRWST)的瞬态特征进行分析,通过与实验结果的对比,阐释了SBLOCA瞬态过程中重要的热工水力现象和非能动系统的行为特性,证明瞬态过程中一些关键参数的预测序列与实验序列达到了较好的吻合度。验证了RELAP5/MOD3.3程序对于分析APEX的SBLOCA的适用性,为先进反应堆非能动安全系统的设计以及反应堆事故缓解能力评估提供参考。更多还原

【Abstract】 AP1000 is a typical GEN-Ⅲ+ passive advanced pressurized water reactor, which uses a passive safety system to discharge the residual heat of the core to ensure the safety of reactor when the conventional residual heat removal system is not available. The Advanced Plant Experiment(APEX) facility is an integral test facility which took AP1000 as a prototype. APEX facility provides important support for the design of AP1000 safety systems and the verification of long-term cooling capability. APEX facility was modeled by RELAP5/MOD3.3 code and set initial and boundary conditions with reference to the experimental conditions of SBLOCA. The key parameters(main loop system performance and transient characteristics of CMT, ACC and IRWST) of main loop system and main equipment in passive core cooling system were analyzed based on operational accident transient. Through the comparison with experimental results,it explains the important thermal hydraulic characteristics and the performance of the passive system in the accident. The comparison shows that the predicted sequence of some key parameters in the transient process is in good agreement with the experimental sequence. A preliminary conclusion is that the RELAP5/MOD3.3 code is applicable to simulate the SBLOCA of APEX. It provides a reference for the design of advanced reactors and passive safety systems and the assessment of reactor accident mitigation capability.更多还原