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二神 敏; 久保 重信; Sofu, T.*; Ammirabile, L.*; Gauthe, P.*
Proceedings of International Conference on Topical Issues in Nuclear Installation Safety; Strengthening Safety of Evolutionary and Innovative Reactor Designs (TIC 2022) (Internet), 10 Pages, 2022/10
In the framework of the GIF, an effort to develop Safety Design Criteria (SDC) for SFR systems was initiated in 2011. For this purpose, an SDC task force (SDC-TF) was formulated in July 2011. The SDC-TF members consist of representatives of CIAE (China), CEA (France), JAEA (Japan), KAERI, KINS (Republic of Korea), IPPE (Russia), ANL, INL, ORNL (United States of America), EC and IAEA. This paper describes the outline of the SDC and SDGs contents and its development background as shown above. These SDC and SDGs refer related IAEA safety standards, such as SSR-2/1 Safety of Nuclear Power Plants: Design, SSG-52 Design of the Reactor Core for Nuclear Power Plants. This paper focuses on both technology neutral aspects, which are common parts between the SDC/SDG and IAEA standards, and SFR specific aspects.
山野 秀将; 久保 重信; 時崎 美奈子*; 中村 博紀*
Proceedings of International Conference on Topical Issues in Nuclear Installation Safety; Strengthening Safety of Evolutionary and Innovative Reactor Designs (TIC 2022) (Internet), 12 Pages, 2022/10
日本で設計された新型ナトリウム冷却高速炉の独特な設計の特徴は、設計拡張状態(DEC)において、受動的炉停止系,受動的崩壊熱除去系(DHRS),異常な過渡時スクラム失敗(ATWS)事象に対する炉内事象終息(IVR)概念である。本論文では、日本で研究された事象シーケンスのための数値解析手法を記述するとともに、典型的なATWS事象に対する受動的炉停止系及び溶融炉心物質のIVRのためのシビアアクシデント対策の有効性を示す。受動的炉停止能力のため、数値解析により、厳しいATWS事象に対して自己作動型炉停止系の有効性を示した。その際、温度応答遅れ時間を流体力学計算(CFD)コードにより評価した。また、デブリベッド冷却性評価のため、最近、3次元CFD解析コードと1次元デブリベッドモジュールを結合させた手法を開発し、受動的DHRSを用いてデブリベッド周辺の3次元流動場を模擬するとともに、コアキャッチャーでのデブリベッド冷却性を示した。
中村 秀夫; Bentaib, A.*; Herranz, L. E.*; Ruyer, P.*; Mascari, F.*; Jacquemain, D.*; Adorni, M.*
Proceedings of International Conference on Topical Issues in Nuclear Installation Safety; Strengthening Safety of Evolutionary and Innovative Reactor Designs (TIC 2022) (Internet), 10 Pages, 2022/10
The WGAMA activity achievements have been published as technical reports, becoming reference materials to discuss innovative methods, materials and technologies in the fields of thermal-hydraulics, computational fluid dynamics (CFD) and severe accidents (SAs). The International Standard Problems (ISPs) and Benchmarks of computer codes have been supported by a huge amount of the databases for the code validation necessary for the reactor safety assessment with accuracy. The paper aims to review and summarize the recent WGAMA outcomes with focus on new advanced reactor applications including small modular reactors (SMRs). Particularly, discussed are applicability of major outcomes in the relevant subjects of passive system, modelling innovation in CFD, severe accident management (SAM) countermeasures, advanced measurement methods and instrumentation, and modelling robustness of safety analysis codes. Although large portions of the outcomes are considered applicable, design-specific subjects may need careful considerations when applied. The WGAMA efforts, experiences and achievements for the safety assessment of operating nuclear power plants including SA will be of great help for the continuous safety improvements required for the advanced reactors including SMRs.