针对船用核动力装置,采用SCDAP/RELAP5最佳估算程序,研究小破口失水事故(SBLOCA)进程,分析破口尺寸对事故的影响;结果显示,破口尺寸的大小对SBLOCA事故进程和后果有较大的影响,破口较小时,依靠投入高压安注系统(...
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The calculation results show that safeguard system of AP1000 can effectively lower the temperature and reduce the pressure of the first loop,also can prevent core overheating. The safety of AP1000 during a small-break loss-of-coolant accident is verified.
分析表明:AP1000的非能动专设安全设施能有效地对一回路进行冷却和降压,防止堆芯过热,验证了AP1000发生冷管段小破口失水事故后的安全性。
参考来源 - AP1000冷管段小破口失水事故分析·2,447,543篇论文数据，部分数据来源于NoteExpress
对小破口失水事故(SBLOCA)及其研究状况进行了综述。
The Small Break Loss of Coolant Accident (SBLOCA) and its research art-of-work are reviewed in this paper.
结果表明，大亚湾核电站采用18个月换料之后，在中小破口失水事故时仍有较大安全裕量。
The results show that the large margin is obtained in Guangdong Nuclear Power Plant with 18-Months fuel cycle.
本文给出了位于上空腔的中小尺寸管道破裂或安全阀意外开启引起的小破口失水事故实验研究。
A simulation experiment of small break loca is introduced, which was caused by the breakdown of a small size or middle size pipe located at upper plenum, or by unexpected opening the safety valve.
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