CAJ | 학술논문

为避免死管段与热分层危害，结合有关经验与核岛工艺系统设计特点，对某新型压水堆一回路各连接管逐一进行死管段与热分层危害分析。筛选出危害可能发生的管段后，对其中典型的热段连接余热导出管段应用计算流体力学软件C FX模拟分析，计算达收敛状态后可得出该管段热分层温度分布情况。另外，该管段下游两个隔离阀间封闭管段初始条件设定为充满工质，因受一回路影响而被加热升温，通过该封闭管段工质最终温度结果可判断是否出现死管段现象。最终计算数据显示热段连接余热导出管段总体上满足热分层验收准则，不过下游隔离阀间封闭管段有形成死管段的风险，但通过调整布置等措施可避免死管段危害。结果还显示出浮力循环流与一回路紊流冲击影响的流线特点。
위피면사관단여열분층위해，결합유관경험여핵도공예계통설계특점，대모신형압수퇴일회로각련접관축일진행사관단여열분층위해분석。사선출위해가능발생적관단후，대기중전형적열단련접여열도출관단응용계산류체역학연건C FX모의분석，계산체수렴상태후가득출해관단열분층온도분포정황。령외，해관단하유량개격리벌간봉폐관단초시조건설정위충만공질，인수일회로영향이피가열승온，통과해봉폐관단공질최종온도결과가판단시부출현사관단현상。최종계산수거현시열단련접여열도출관단총체상만족열분층험수준칙，불과하유격리벌간봉폐관단유형성사관단적풍험，단통과조정포치등조시가피면사관단위해。결과환현시출부력순배류여일회로문류충격영향적류선특점。
To avoid dead pipe segment and thermal stratification hazard ,the dead pipe segment and thermal stratification hazards among primary loop related pipes for new type PWR based on experience and nuclear island system design features were analyzed in the paper . Having screened out those pipes in w hich the hazard could occur , the residual heat removal pipe CFX simulation was carried out typically .Final results show thermal stratification temperature distribution and dow nstream pipe segment temperature rising between two isolation valves filled with coolant originally . In conclusion , the residual heat removal pipe meets the requirements of thermal stratification criteria generally , and the dead pipe segment hazard may occur in pipe segment between two isolation valves , but could be prevented by means of layout adjustment . Besides , results show the characteristics of buoyancy recirculation and vortex impingement from primary loop flow on residual heat removal pipe .