VVER机组事故分析耦合程序开发及应用OA
Development and Application of Accident Analysis Coupled Code for VVER Units
针对VVER机组尤其是核热耦合作用强烈和局部功率分布变化显著的事故分析,本研究开发了物理热工耦合程序.采用动态链接库技术并编制耦合接口模块,实现三维中子动力学程序和热工水力系统程序的耦合.在此基础上,本研究开展了VVER-1000机组硼酸误稀释事故的瞬态模拟,分析事故进程和一、二回路参数随时间的变化.最后,评估了重要安全参数与验收准则的符合情况.结果表明:耦合程序的模拟结果与电厂实测值符合得较好.事故分析所获得的物理热工参数的变化趋势与FSAR总体上具有一致性,极值相差较小.验证了所开发的耦合程序计算能力和可靠性.燃料最高温度和最小DNBR等均满足验收准则的要求.本研究所开发的物理热工耦合程序为VVER机组事故分析提供了有效可靠的模拟工具.
Neutronics/thermal-hydraulic coupled code was developed to model the accidents for VVER units especially in which strong neutronics/thermal coupling effect and obvious change of local power distribution exist.Through dynamic link library technology and building coupling interface model,three-dimensional neutronic kinetics code and thermal-hydraulic code were coupled.Transient simulation on the inadvertent dilution of boric acid accident of VVER-1000 units was carried out based on the coupled code.The sequence of event and parameters in the primary and second circuits were analyzed.Finally,compliance of critical safety-relevant parameters with acceptance criteria was evaluated.Results indicate that simulated values obtained by the coupled code agree well with measured data of the power plant.Variation trends of neutronic and thermal-hydraulic parameters present overall consistence with those of FSAR,and the deviation of the extreme values is small.The computing performance and reliability of the coupled code were proved.Safety acceptance criteria related to maximum fuel temperature,minimum DNBR and other values are satisfied.Neutronics/thermal-hydraulic coupled code could be used as an effective tool for accurate accident modeling of VVER units.
陈静;陈超;蒋校丰;任一飞;张健夫
江苏核电有限公司,连云港 222042||上海核星核电科技有限公司,上海 201103上海核星核电科技有限公司,上海 201103上海核星核电科技有限公司,上海 201103江苏核电有限公司,连云港 222042江苏核电有限公司,连云港 222042
能源科技
VVER机组事故分析物理热工耦合硼酸误稀释
VVER unitsaccident analysisneutronics/thermal couplinginadvertent dilution of boric acid
《核安全》 2026 (1)
1-9,9
中核集团"青年英才"项目
评论