首页> 外文会议>14th International Conference on Nuclear Engineering 2006(ICONE14) vol.3 >Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors (9) System Outline and Endurance Test of Low-Pressure Steam Injectors
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Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors (9) System Outline and Endurance Test of Low-Pressure Steam Injectors

机译:高效蒸汽喷射器创新简化核电站技术的发展(9)系统概述和低压蒸汽喷射器的耐久性测试

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A Steam Injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater. This provides SI with capability to serve also as a direct-contact feedwater heater that heats up feedwater by using extracted steam from the turbine. We are developing technology for "Innovative Simplified Nuclear Power Plants" in order to further improve the economy and safety of nuclear power plants. Our technology development aims to significantly simplify equipment and reduce physical quantities by applying "High-Efficiency SI", which are applicable to a wide range of operation regimes beyond the performance and applicable range of existing SIs and enables unprecedented multistage and parallel operation, to the low-pressure feedwater heaters and Emergency Core Cooling Systems (ECCS) of nuclear power plants, as well as achieve high inherent safety to prevent severe accidents by keeping the core covered with water (a Severe Accident-Free Concept). The innovative-simplified nuclear power plant consists of a simplified feedwater heating system, a passive core injection system and a passive containment cooling system. This report describes the results of the endurance and performance tests of low-pressure SIs for feedwater heaters with Jet-deaerator and core injection system. A part of this report are fruits of research which is carried out by Tokyo Electric Power Company (TEPCO), Toshiba, and 7 Universities in Japan, funded from the Ministry of Economy, Trade and Industry (METI) of Japan as the national public research-funded program.
机译:蒸汽喷射器(SI)是一种简单,紧凑且被动的泵,还可以充当高性能的直接接触式紧凑型加热器。这使SI具有用作直接接触式给水加热器的能力,该加热器通过使用从涡轮机提取的蒸汽来加热给水。我们正在为“创新型简化核电站”开发技术,以进一步改善核电站的经济性和安全性。我们的技术开发旨在通过应用“高效SI”来显着简化设备并减少物理量,“高效SI”适用于除现有SI的性能和适用范围之外的多种运行方式,并实现前所未有的多级和并行操作。核电厂的低压给水加热器和紧急堆芯冷却系统(ECCS),以及通过使堆芯被水覆盖而实现很高的固有安全性,以防止严重事故(严重无事故概念)。创新简化的核电站包括简化的给水加热系统,无源堆芯注入系统和无源安全壳冷却系统。该报告描述了带有喷射除气器和注芯系统的给水加热器的低压SI的耐久性和性能测试的结果。本报告的一部分是由东京电力公司(TOPCO),东芝和日本的7所大学进行的研究成果,由日本经济产业省(METI)作为国家公共研究资助资助的计划。

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