日本超临界水资源研究回顾

Yoshiaki Oka
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摘要

SCWR(超临界水冷反应堆)是第四代反应堆之一。本综述总结了作者领导的东京大学和早稻田大学团队从 1989 年到 2014 年通过数值模拟开发 SCWR 设计概念的成果。其中包括堆芯设计、子通道分析、统计热设计、燃料棒设计、燃料完整性标准的制定、电站系统和热平衡、电站动力学分析、电站控制、启动系统、稳定性分析、安全原理、安全标准、安全分析、瞬态子通道分析和快堆重水堆。随后简要介绍了热水力学、材料和水化学方面的实验结果。讨论内容包括日本生物质压水堆制造商进行的重水堆研究、对 2005 INEEL 重水堆报告的评论、对重水堆的误解以及商业化挑战。超临界水力发电反应堆是轻水反应堆的一项创新,它以超临界燃煤发电厂技术为基础,已在全球使用了半个多世纪。本综述涵盖了 SCWR 设计和分析的大部分内容。对于研究人员来说,这是了解轻水反应堆设计和分析的一个很好的课题。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Review of SCWR research in Japan
SCWR (supercritical water cooled reactor) is one of the Generation IV reactors. This review summarizes the results of SCWR design concept development through numerical simulations carried out by the author-led team at the University of Tokyo and Waseda University from 1989 to 2014. They are core design, subchannel analysis, statistical thermal design, fuel rod design, development of fuel integrity criteria, plant system and heat balance, plant dynamics analysis, plant control, startup system, stability analysis, safety principle, safety criteria, safety analysis, transient subchannel analysis and fast reactor SCWR. A brief summary of experimental results on thermal hydraulics, materials and water chemistry follows. Discussion includes SCPR study by Japanese BWR manufacturers, comments on the 2005 INEEL SCWR report, misconceptions about SCWR and commercialization challenges. The SCWR is an innovation in light water reactors based on supercritical coal-fired power plant technology that has been in use worldwide for over half a century. This review covers most of the SCWR design and analysis. For researchers, it is a good subject to understand the design and analysis of light water reactors.
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