原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2013年
9期
1514-1521
,共8页
王宝生%王冬青%董化平%姜晶%张建民
王寶生%王鼕青%董化平%薑晶%張建民
왕보생%왕동청%동화평%강정%장건민
A P1000%非能动余热排出系统%自然循环%全厂断电%瞬态分析
A P1000%非能動餘熱排齣繫統%自然循環%全廠斷電%瞬態分析
A P1000%비능동여열배출계통%자연순배%전엄단전%순태분석
AP1000%passive residual heat removal system%natural circulation%station blackout%transient analysis
在一维质量、动量和能量守恒方程基础上建立了A P1000反应堆主冷却剂系统及非能动余热排出系统数学模型,并编制了用于该系统瞬态特性分析的动态仿真程序PRHRSDSC。模拟了非能动余热排出系统在全厂断电事故下的瞬态响应过程,并将计算结果与西屋公司的 LOFTRAN程序结果进行对比。结果表明:系统可依靠自然循环有效导出堆芯余热,一回路冷却剂温度维持在过冷状态,峰值压力未超过运行压力限值,各参数的变化趋势符合良好,证明了建模的合理性。
在一維質量、動量和能量守恆方程基礎上建立瞭A P1000反應堆主冷卻劑繫統及非能動餘熱排齣繫統數學模型,併編製瞭用于該繫統瞬態特性分析的動態倣真程序PRHRSDSC。模擬瞭非能動餘熱排齣繫統在全廠斷電事故下的瞬態響應過程,併將計算結果與西屋公司的 LOFTRAN程序結果進行對比。結果錶明:繫統可依靠自然循環有效導齣堆芯餘熱,一迴路冷卻劑溫度維持在過冷狀態,峰值壓力未超過運行壓力限值,各參數的變化趨勢符閤良好,證明瞭建模的閤理性。
재일유질량、동량화능량수항방정기출상건립료A P1000반응퇴주냉각제계통급비능동여열배출계통수학모형,병편제료용우해계통순태특성분석적동태방진정서PRHRSDSC。모의료비능동여열배출계통재전엄단전사고하적순태향응과정,병장계산결과여서옥공사적 LOFTRAN정서결과진행대비。결과표명:계통가의고자연순배유효도출퇴심여열,일회로냉각제온도유지재과랭상태,봉치압력미초과운행압력한치,각삼수적변화추세부합량호,증명료건모적합이성。
Based on one-dimensional governing equations , the mathematical models of the reactor primary coolant system and the passive residual heat removal system (PRHRS) were established .A dynamic simulation program PRHRSDSC was developed to analyze the transient characteristics of the system .The program was used to simulate the transient process of PRHRS during station blackout accident .The calculated results were compared with LOFTRAN code .The results show that the core residual heat can be removed efficiently using natural circulation to keep the coolant at sub-cooled state and the peak pressure is below the limit of the operation pressure .T he parameter varia-tion trends are well consistent with LOFTRAN code and the rationality of the model is demonstrated .