CAJ | 학술논문

三门核电A P1000反应堆在满功率情况下发生汽轮机故障停机事件时，通过快速降功率系统、旁排系统和棒控系统等的快速响应，一回路的参数不会突破安全限值，避免了反应堆停堆，降低了该瞬态对反应堆冷却剂系统的冲击。文章对停机不停堆的实现方式和运行特点进行了详细的分析和阐述，以帮助电站人员对停机不停堆的理解，并提高他们面临瞬态的响应能力。
삼문핵전A P1000반응퇴재만공솔정황하발생기륜궤고장정궤사건시，통과쾌속강공솔계통、방배계통화봉공계통등적쾌속향응，일회로적삼수불회돌파안전한치，피면료반응퇴정퇴，강저료해순태대반응퇴냉각제계통적충격。문장대정궤불정퇴적실현방식화운행특점진행료상세적분석화천술，이방조전참인원대정궤불정퇴적리해，병제고타문면림순태적향응능력。
Reactor is tripped after turbine trip in generate II plant, which prevents the temperature, pressure and water level of reactor coolant system exceeding safety limits and protect the safety of reactor. While Sanmen nuclear power plant is designed to sustain a turbine trip from 100-percent power, without generating a reactor trip, the rapid power reduction system, in conjunction with automatic steam dump control system, and rod control system, is provided to accommodate this abnormal load rejection and to reduce the effects of the transient imposed on the reactor coolant system. In this paper, the design and operation characteristics of turbine trip without reactor trip are analyzed and explained in detail to facilitate the understanding of the concept of turbine trip without reactor trip, and to improve the response ability of plant personnel in the transient.