部門設立30周年記念出版 Vol.3

（ナトリウム冷却高速炉の開発－社会実装に向けた熱流動・安全性研究）

抄録

The book, JSME Series in Thermal and Nuclear Power Generation Vol.3 Sodium-cooled Fast Reactor, was published as a 30th anniversary memorial project of Power & Energy Systems Division. The book is a collection of the past experience of design, construction, and operation of the experimental reactor “Joyo” and the prototype reactor “Monju”, the latest knowledge including related research and development activities and technology for SFR designs, and the future prospects of SFR development in Japan, looking back the history of development of fast reactors started in the early 1960s. This paper describes an introduction of the book on a part of key technologies regarding safety assessment, thermal-hydraulics, neutronics, and fuel and material development. As a new way forward to achieve a social implementation of SFR, this introductory paper also provides an overview of an integrated evaluation system named “ARKADIA” to offer the best possible solutions for challenges arising during the design process, safety assessment, and operation of a nuclear plant over its life cycle, in active use of the R&D efforts and knowledges on thermal-hydraulics and safety assessment with state-of-the-art numerical analysis technologies.