The knowledge management on the design of a generation IV sodium fast reactor project at CEA. The case and methodology applied on the Astrid project

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI:10.1051/epjn/2020016
G. Rodriguez, Philippe Amphoux, D. Plancq, E. Richebois, F. Varaine, Philippe Bigeon
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Abstract

From 2010 to 2019, the French Alternative Energies and Atomic Commission (CEA) associated with industrial partners realized the Basic Design of a prototype Sodium Fast Reactor. This project was called ASTRID (ASTRID for Advanced Sodium Technological Reactor for Industrial Demonstration). ASTRID design studies were financed through governmental funds until the end of the basic design. These funds covered also the design studies for the core manufacturing workshop, the refurbishment or construction of large test loops. One year before the term of this Basic Design phase (in 2018), industrial partners, CEA and the French State conducted a review of fast neutrons reactors and fuel cycle strategy. The review which is now translated into the Multiannual Energy Program concluded that the perspective of industrial deployment of Fast Reactors is more distant. Yet it has been concluded to keep this option open, requiring to maintain competences, and to progress on technological barriers and further develop know-how. The strategy for complete closure of nuclear fuel cycle is maintained as a long-term sustainability objective (in the second half of the 21st century). Therefore, as a direct consequence of this decision, the ASTRID project stopped at the end of 2019 at its Basic Design phase. Quickly the question raised on the Knowledge Management (KM) and Know-How capitalization of the huge amount of studies and results realized during ten years (around 23 000 technical documents). Moreover the challenge was to realize this KM process in less than one year, before the ASTRID project team definitive split. The paper is presenting an innovative KM methodology which has been created and specifically performed on the ASTRID project. It is based on a series of interviews and video recordings, all transformed into some New KM tools called “MOOK” (MOOK for Management of Organized Online Knowledge). All these MOOKs considered as “data rich contents” are then inter-connected and linked by the ASTRID Product Breakdown Structure to some fundamental documents, for a comprehensive and quick mapping of the project. They finally form an efficient KM tool recorded in a PLM Software (PLM for Product Lifecycle Management). Thus the ASTRID project team has realized a high level and easy-to-use “GPS” (Global Positioning System) tool to keep the ASTRID history, context, knowledge and know-how for years. This KM methodology can be easily adapted to other nuclear projects and needs.
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东航第四代钠快堆项目设计中的知识管理。应用于Astrid项目的案例和方法
从2010年到2019年,法国替代能源和原子能委员会(CEA)与工业合作伙伴一起实现了钠快堆原型的基本设计。这个项目被称为ASTRID(先进钠技术反应堆工业示范)。ASTRID设计研究由政府基金资助,直至基本设计结束。这些资金还用于核心制造车间的设计研究、大型试验回路的翻新或建造。在基本设计阶段的前一年(2018年),工业合作伙伴、CEA和法国政府对快中子反应堆和燃料循环战略进行了审查。现在被翻译成《多年度能源计划》(Multiannual Energy Program)的这份评估报告得出的结论是,快速反应堆的工业部署前景更为遥远。然而,结论是保留这一选择,要求保持能力,并在技术壁垒方面取得进展并进一步发展专门知识。完全关闭核燃料循环的战略作为一项长期可持续性目标(在21世纪下半叶)得以维持。因此,作为这一决定的直接后果,ASTRID项目于2019年底在其基本设计阶段停止。很快就提出了关于知识管理(KM)和专有技术资本化的问题,这是十年来实现的大量研究和成果(大约23000份技术文件)。此外,挑战是在ASTRID项目团队最终分裂之前,在不到一年的时间内实现这个KM过程。本文介绍了一种创新的知识管理方法,该方法已被创建并专门用于ASTRID项目。它是基于一系列的访谈和视频记录,所有这些都转化为一些新的知识管理工具,称为“MOOK”(MOOK for Management of Organized Online Knowledge)。所有这些被认为是“数据丰富内容”的mook,然后通过ASTRID产品分解结构相互连接并链接到一些基本文档,以便全面快速地映射项目。它们最终形成一个有效的知识管理工具,记录在PLM软件(PLM for Product Lifecycle Management)中。因此,ASTRID项目团队已经实现了一个高水平和易于使用的“GPS”(全球定位系统)工具,以保持ASTRID的历史,背景,知识和技术多年。这种知识管理方法可以很容易地适用于其他核项目和需求。
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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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