France–Japan synthesis concept on sodium-cooled fast reactor review of a joint collaborative work

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2021-01-01 DOI:10.1051/epjn/2021014
G. Rodriguez, F. Varaine, L. Costes, C. Venard, F. Serre, F. Chanteclair, Marie-Sophie Chenaud, F. Dechelette, E. Hourcade, D. Plancq, Jean Hamy, Jean-François Dirat, B. Carluec, B. Perrin, D. Verrier, S. Kubo, N. Ishikawa, Masaaki Tanaka, K. Takano, S. Ohki, T. Ozawa, H. Yamano, Yoshio Shimakawa, H. Mochida, R. Shimizu, S. Kosaka, Yumi Yamada, K. Koyama, Hisatomo Murakami, T. Iitsuka, K. Oyama, Fumiaki Kaneko, Koichi Higurashi, K. Kurita
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引用次数: 2

Abstract

In the frame of the France-Japan agreement on nuclear collaboration, a bilateral collaboration agreement on nuclear energy was signed on March 21st, 2017, including a topic dedicated to Sodium-cooled Fast Reactor (SFR). This agreement has set the framework to start a bilateral discussion on a joint view of an SFR concept. France (CEA and FRAMATOME) and Japan (JAEA, MHI and MFBR) have carried out these studies from 2017 to 2019. Based on the beginning of the basic design phase of ASTRID project − ASTRID − 600 MWe (ASTRID for Advanced Sodium Technological Reactor for Industrial Demonstration), the two countries performed a common work to examine ways to develop a feasible common design concept, which could be realized both in France and in Japan. The subject was then extended and extrapolated with the ASTRID − 150 MWe data (reduced power reactor and enhanced experimental capabilities) in a second phase of this study. France and Japan first focused on design requirements. Common requirements were identified, as well as differences in the safety approach and the structural design requirements, according to national standards and respective site conditions, in particular considering seismic hazards. The teams developed common Top-Level design Requirements (TLRs) to allow common specification data, then joint design. This collaborative work was carried out through the implementation of twelve France-Japan Working Groups, working jointly. This paper is providing a review of this joint synthesis on Sodium Fast Reactor design concept. It is summarizing the context and objectives, then the definition and approaches of the Top Level Requirements. This paper is then dealing with the major design features: the core design and their related safety aspects, and the nuclear island design. Thus, this paper is providing a comprehensive review of this joint work gathering French and Japan nuclear design teams during two full years.
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法日在钠冷快堆合成概念上的联合协作工作综述
在《法日核合作协议》框架下,两国于2017年3月21日签署了一项双边核能合作协议,其中包括钠冷快堆(SFR)专题。该协议为启动关于共同看待SFR概念的双边讨论奠定了框架。法国(CEA和FRAMATOME)和日本(JAEA, MHI和MFBR)从2017年到2019年进行了这些研究。基于ASTRID - 600 MWe (ASTRID为工业示范先进钠技术反应堆)项目基本设计阶段的开始,两国开展了一项共同工作,以研究开发可行的共同设计概念的方法,该概念可以在法国和日本实现。然后,在本研究的第二阶段,使用ASTRID−150 MWe数据(降低反应堆功率和增强实验能力)扩展和外推该主题。法国和日本首先关注的是设计要求。根据国家标准和各自的场地条件,特别是考虑到地震危险,确定了共同的要求,以及安全方法和结构设计要求的差异。团队开发了通用的顶层设计需求(tlr),以允许通用的规范数据,然后进行联合设计。这一协作工作是通过12个法日工作组共同开展的。本文对这种联合合成钠快堆的设计理念进行了综述。它总结了上下文和目标,然后是顶层需求的定义和方法。本文接着论述了设计的主要特点:堆芯设计及其相关安全方面的设计,以及核岛设计。因此,本文对法国和日本核设计团队历时两年的联合工作进行了全面回顾。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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