ACME台架全厂断电事故试验研究  

Test Study of Station Blackout Accident on Advanced Core-cooling Mechanism Experiment Facility

作　　者：刘宇生[1] 许超 房芳芳 靖剑平[1] 王楠 安婕铷 LIU Yusheng;XU Chao;FANG Fangfang;JING Jianping;WANG Nan;AN Jieru(Nuclear and Radiation Safety Center,Ministry of Environmental Protection,Beijing 100084,China;State Nuclear Power Technology R＆D Center,Beijing 1@22@9,China)

机构地区：[1]环境保护部核与辐射安全中心,北京100084 [2]国核华清(北京)核电技术研发中心有限公司,北京102209

出　　处：《原子能科学技术》2018年第8期1438-1444,共7页Atomic Energy Science and Technology

基　　金：国家科技重大专项资助项目(2015ZX06002007-001)

摘　　要：为研究AP型非能动核电厂全厂断电事故下的运行特性,利用大型非能动堆芯冷却系统整体试验(ACME)台架开展了试验研究,分析了主要的试验进程和关键参数的变化特点。研究结果表明:ACME台架全厂断电试验的事故序列及试验现象与已有分析一致,符合预期,试验再现了AP型非能动核电厂全厂断电的事故进程;在整个事故过程中,稳压器水位升高,但未发生满溢,非能动余热排出(PRHR)系统换热功率可与衰变功率达到平衡,堆芯余热可有效载出;堆芯补水箱(CMT)和安全壳内置换料水箱(IRWST)初始条件对非能动余热排出阶段的事故进程具有重要影响,在1列CMT投入失效或IRWST异常等不利初始条件下,模化后的非能动堆芯冷却系统(PXS)仍可满足事故验收准则。To study the performance characteristics of AP type passive nuclear power plant under typical station blackout（SBO）condition,the SBO integral tests were conducted on the Advanced Core-cooling Mechanism Experiment（ACME）facility.The accident sequences and key parameters during SBO tests were investigated.The results show that the ACME SBO tests represent the typical SBO accident progress of AP type passive nuclear power plant.The main sequences and thermal-hydraulic phenomena of ACME SBO tests are consistent with those of pre-analysis,and the test results therefore are as to be expected.The water level in pressurizer is raised by volume change of coolant in reactor coolant system（RCS）.However the pressurizer does not overflow during the whole test process.Besides,the power of passive residual heat removal heatexchanger（PRHR HX）and that of decay heat can reach a balance.The core decay heat can be transported effectively and continuously.The initial conditions of core makeup tank（CMT）and in-containment refueling water storage tank（IRWST）play an important role in passive residual heat removal phase of accident progress.When one CMT is failed or the temperature and level of cooling water in IRWST are abnormal,the performance of scaled down passive core cooling system（PXS）still can satisfy the accident acceptance criteria.

关 键 词：全厂断电 ACME台架 整体试验 非能动安全 

分 类 号：TL333[核科学技术—核技术及应用] TL364.4