首页> 外文会议>Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs, Feb 18-20, 2002, Paris, France >SAFETY ISSUES OF REDUCED-MODERATION WATER REACTOR AND HIGH TEMPERATURE GAS-COOLED REACTOR DEVELOPED AT JAERI
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SAFETY ISSUES OF REDUCED-MODERATION WATER REACTOR AND HIGH TEMPERATURE GAS-COOLED REACTOR DEVELOPED AT JAERI

机译:杰里开发的降温水反应器和高温气冷反应器的安全问题

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As advanced reactors, reduced-moderation water reactor (RMWR) and high temperature gas-cooled reactor (HTGR) are being developed at the Japan Atomic Energy Research Institute (JAERI). RMWR aims at achievement of a high conversion ratio and negative void reactivity coefficients with MOX fuels, based on well-experienced water-cooled reactor technology. Safety issues important for RMWR are thermal hydraulic safety on the tight-lattice core including stability, highly enriched MOX fuel behaviors at high burn-up, and plant system safety including passive components. Related experiments and analysis have been conducted to obtain information required for the design optimization and safety confirmation. Based on the experiences of design, construction and operation of High Temperature Engineering Test Reactor (HTTR), design study on the Gas Turbine High Temperature Reactor 300 (GTHTR 300) has been conducted, with greatly simplified system, including safety systems due to its inherent safety. As major safety issues, severe accident free and demonstrable safety are proposed. This new safety philosophy is to avoid most accidents and to greatly reduce the probability of severe accidents compared with that of current power reactors.
机译:作为先进的反应堆,日本原子能研究所(JAERI)正在开发减温水堆(RMWR)和高温气冷堆(HTGR)。基于经验丰富的水冷反应堆技术,RMWR的目标是利用MOX燃料实现高转化率和负空隙反应系数。对于RMWR而言,重要的安全问题是紧密晶格堆芯上的热液压安全性,包括稳定性,高燃耗时高浓度的MOX燃料行为以及包括被动组件在内的工厂系统安全性。已经进行了相关的实验和分析,以获得设计优化和安全确认所需的信息。根据高温工程试验反应堆(HTTR)的设计,建造和运行经验,对燃气轮机高温反应堆300(GTHTR 300)进行了设计研究,由于其固有的固有特性,大大简化了系统,包括安全系统安全。作为主要的安全问题,提出了无严重事故和可证明的安全性。与当前的动力堆相比,这种新的安全理念是避免大多数事故并大大降低发生严重事故的可能性。

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