首页> 外文会议>ASME·JSME Thermal Engineering Joint Conference >HEAT REMOVAL PERFORMANCE OF PASSIVE CONTAINMENT COOLING SYSTEM IN THE NEXT GENERATION BOILING WATER REACTOR
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HEAT REMOVAL PERFORMANCE OF PASSIVE CONTAINMENT COOLING SYSTEM IN THE NEXT GENERATION BOILING WATER REACTOR

机译:下一代沸水反应器中被动遏制冷却系统的散热性能

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In the next generation light water reactors, the adoption of a passive system concept is proposed, which can enhance safety system reliablity and plant simplicity. The passive containment cooling system (PCCS) removes the decay heat following an accident without any operational actions. Toshiba has proceeded with the development of study program for the PCCS from the thermal-hydraulic viewpoint. The program includes mainly a testing program using a full-height, integral system test facility GIRAFFE as well as supplemental basic test programs. The results of these testing have shown that the PCCS has heat removal capability sufficient to prevent the containment from exceeding the design pressure following an accident, and that the PCCS is a promising concept to enhance plant safety for the next generation nuclear reactors.
机译:在下一代轻型水反应堆中,提出了一种被动系统概念,可以增强安全系统释放和工厂简单性。无源电容冷却系统(PCCS)在没有任何操作动作的情况下在发生事故后去除衰减热量。东芝已经开始开发来自热液压观点的PCCS的研究计划。该计划主要包括使用全高,整体系统测试设施长颈鹿以及补充基本测试程序的测试程序。这些测试的结果表明,PCCS具有足以防止遏制在事故之后超过设计压力的热除去能力,并且PCCS是提高下一代核反应堆的植物安全性的有希望的概念。

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