CAJ | 학술논문

AP1000有其固有的安全性能，由于采用非能动安全系统，大大降低了发生人因错误的可能性。文章简要介绍了美国西屋公司的核电站仿真软件PCTRAN/AP1000，针对我国将建造的先进非能动AP1000的第三代核电站验证其固有安全性。本文使用PCTRAN/AP1000软件对设计基准事故冷却剂泵卡轴（转子卡死）进行模拟仿真。仿真结果表明，PCTRAN能够正确反映核电站的运行特性，在设计基准事故仿真方面尤有特色，验证了AP1000的固有的安全性。
AP1000유기고유적안전성능，유우채용비능동안전계통，대대강저료발생인인착오적가능성。문장간요개소료미국서옥공사적핵전참방진연건PCTRAN/AP1000，침대아국장건조적선진비능동AP1000적제삼대핵전참험증기고유안전성。본문사용PCTRAN/AP1000연건대설계기준사고냉각제빙잡축（전자잡사）진행모의방진。방진결과표명，PCTRAN능구정학반영핵전참적운행특성，재설계기준사고방진방면우유특색，험증료AP1000적고유적안전성。
AP1000 has its inherent safety performance, and the application of the non kinetic energy security system greatly reduces the occurrence of human error probability. This paper simply introduces the nuclear power plant simulation software PCTRAN/AP1000 of American Westinghouse Electric Manufacturing Company and verifies the inherent safety of the third-generation nuclear power plant that will be built in China with advanced non kinetic AP1000. This article carries on the simulation on the design basis accident of coolant pump clamping shaft (rotor locked) applying the PCTRAN / AP1000 software. The simulation results show that PCTRAN can correctly reflect the operating characteristics of nuclear power plant and is especially distinctive in terms of design basis accident simulation. The inherent safety of AP1000 is verified in this paper.