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首页> 外文期刊>Nuclear Engineering and Design >Boiling water reactor with innovative safety concept: The Generation III+ SWR-1000
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Boiling water reactor with innovative safety concept: The Generation III+ SWR-1000

机译:具有创新安全概念的沸水反应堆:Generation III + SWR-1000

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摘要

AREVA NP has developed an innovative boiling water reactor (BWR) SWR-1000 in close cooperation with German nuclear utilities and with support from various European partners. This Generation III+ reactor design marks a new era in the successful tradition of BWR and, with a net electrical output of approximately 1250 MWe, is aimed at ensuring competitive power generating costs compared to gas and coal fired stations. It is particularly suitable for countries whose power networks cannot facilitate large power plants. At the same time, the SWR-1000 meets the highest safety standards, including control of core melt accidents. These objectives are met by supplementing active safety systems with passive safety equipment of various designs for accident detection and control and by simplifying systems needed for normal plant operation on the basis of past operating experience. The plant is also protected against airplane crash loads. The functional capabilities and capacities of all new systems and components were successfully tested under realistic and conservative boundary conditions in large-scale test facilities in Finland, Switzerland and Germany. In general, the SWR-1000 design is based on well-proven analytical codes and design tools validated for BWR applications through recalculation of relevant experiments and independent licensing activities performed by authorities or their experts. The overview of used analytical codes and design tools as well as performed experimental validation programs is presented. Effective implementation of passive safety systems is demonstrated through the numerical simulation of transients and loss of coolant accidents (LOCAs) as well as through analytical simulation of a severe accident associated with the core melt. In the LOCA simulation presented the existing active core flooding systems were not used for emergency control: only passive systems were relevant for the analyses. Despite this - no core heat-up occurred. In the case of reactor core melting numerically is demonstrated that the molten core debris would be retained inside the reactor vessel due to the effective passive external water cooling of the vessel, keeping it completely intact. A short construction period of just 48 months from first concrete to provisional take over, flexible fuel cycle lengths of between 12 and 24 months and a high fuel discharge burn-up all contribute towards meeting economic goals. Realistic average availability for a plant lifetime of 60 years and 12 months cycle is 94.5%. Systems and plant design were reviewed by expert groups of European utilities. With the SWR-1000, AREVA NP has developed a design concept for a BWR plant that is now ready for commercial deployment and which fully meets the most stringent international requirements in terms of nuclear safety and nuclear regulatory.
机译:在与德国核电公司的密切合作下,并得到了众多欧洲合作伙伴的支持,阿海珐NP公司开发了创新的沸水反应堆(BWR)SWR-1000。第三代+反应堆设计标志着BWR成功传统的一个新时代,其净电力输出约为1250 MWe,旨在确保与天然气和燃煤电站相比具有竞争力的发电成本。它特别适用于电网无法为大型电厂提供便利的国家。同时,SWR-1000符合最高安全标准,包括控制熔芯事故。通过为主动安全系统补充各种设计用于事故检测和控制的被动安全设备,以及根据过去的操作经验简化工厂正常运行所需的系统,可以实现这些目标。该工厂还受到保护,以防飞机坠毁。所有新系统和组件的功能能力均在现实和保守的边界条件下在芬兰,瑞士和德国的大型测试设施中成功进行了测试。通常,SWR-1000设计基于经过广泛验证的分析代码和设计工具,通过重新计算相关实验和主管部门或其专家进行的独立许可活动,这些设计工具已针对BWR应用进行了验证。介绍了使用的分析代码和设计工具以及执行的实验验证程序的概述。通过瞬态和冷却剂事故损失(LOCA)的数值模拟以及与堆芯熔体相关的严重事故的分析模拟,证明了被动安全系统的有效实施。在LOCA模拟中,现有的主动堆芯驱油系统未用于紧急控制:只有被动系统与分析有关。尽管这样-没有发生核心加热。在反应堆堆芯熔化的情况下,通过数值证明,由于容器的有效被动外部水冷,熔融堆芯碎片将保留在反应堆容器内部,从而使其完全完好无损。从最初的混凝土到临时接管仅48个月的短建设期,在12到24个月之间的灵活燃料循环长度以及很高的燃耗排放量都有助于实现经济目标。工厂的60年寿命和12个月周期的实际平均可用性为94.5%。欧洲公用事业专家小组对系统和工厂设计进行了审查。凭借SWR-1000,AREVA NP为BWR工厂开发了一种设计理念,该工厂现已准备好进行商业部署,并且完全满足国际上在核安全和核监管方面最严格的要求。

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