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Evaluation Study of NPPs Design Improvement Based on SGTR Calculation Result

机译:基于SGTR计算结果的核电厂设计改进评价研究

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CP1000, improved from 2nd generation nuclear power plant technology, is a new concept of 2nd plus technology, some improvements of which are relatively mature. Based on the technology of 2nd plus, two new design improvements are being implemented, substituting high pressure safety injection with middle pressure safety injection and adding a function of fast cooling when an accident happens. Using code RELAP5, this article calculated and analyzed SGTR accident in order to evaluate the impact of the two improvements.
机译:CP1000是第二代核电站技术的改进,是第二代技术的新概念,其中一些改进已经相对成熟。基于2nd plus的技术,正在实施两项新的设计改进:用中压安全注入代替高压安全注入,并在发生事故时增加快速冷却功能。本文使用代码RELAP5,对SGTR事故进行了计算和分析,以评估这两项改进的影响。

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