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Journal Articles

Development of severe accident simulation code for sodium-cooled fast reactors: SIMMER-V, 1; Overview of the SIMMER-V code development

Tagami, Hirotaka; Ishida, Shinya; Okano, Yasushi; Yamano, Hidemasa; Kubo, Shigenobu; Payot, F.*; Saas, L.*; Trotignon, L.*; Gubernatis, P.*; Dufour, E.*; et al.

Proceedings of 11th European Review Meeting on Severe Accident Research Conference (ERMSAR 2024) (Internet), 12 Pages, 2024/05

JAEA has been developing the SIMMER-V code in collaboration with CEA to perform severe accident (SA) simulations of future sodium-cooled fast reactors (SFRs) including a unique core design with large-scale heterogeneous cores. An SA sequence in SFRs has been analyzed by: the SAS4A code for the Initiation Phase (IP), in which fuel pin disruption and vertical fuel dispersion occur in individual fuel subassemblies; and the two-dimensional SIMMER-III or three-dimensional SIMMER-IV code for the Transition Phase (TP), in which core disruption extends to the whole core. The joint development of SIMMER-V is of limited scope but aims at significantly expanding the code applicability by providing flexible interfaces to couple a SIMMER-V calculation with other computational domains or other codes, and by adding new advanced physical models such as a detailed fuel pin model and a model of flexible treatment of fuel isotopic composition. The former tasks are conducted by CEA the latter tasks by JAEA. In parallel to the code development, verification and validation of the new models and methods have been performed. This paper describes the objectives and overall framework of SIMMER-V code development program, representative new elements, and recent development progress.

Journal Articles

A Summary of sodium-cooled fast reactor development

Aoto, Kazumi; Dufour, P.*; Hongyi, Y.*; Glats, J. P.*; Kim, Y.-I.*; Ashurko, Y.*; Hill, R.*; Uto, Nariaki

Progress in Nuclear Energy, 77, p.247 - 265, 2014/11

 Times Cited Count:147 Percentile:99.64(Nuclear Science & Technology)

Much of the basic technology for the Sodium-cooled fast Reactor (SFR) has been established through long term development experience with former fast reactor programs, and is being confirmed by the Ph$'e$nix end-of-life tests, the restart of Monju, the lifetime extension of BN-600 and the startup of CEFR. Planned startup in 2014 for BN-800 and PFBR will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under development. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing for the Generation-IV SFR development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.

Journal Articles

Outline of the SFR component design and BOP project plan in the generation IV R&D programme

Konomura, Mamoru; Kim, S.-O.*; Hill, R.*; Dufour, P.*; Lennox, T.*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

On a basis of Generation IV nuclear energy system, various R&D project plans for sodium cooled reactor have been drawn up including component design and balance of plant (CD and BOP). At present, CD and BOP for the reference SFR systems can be largely established from the existing knowledge and operation experience. Therefore, the project plan for CD and BOP R&D for Generation IV system is related to the system performance and the development of alternatives to the reference systems for enhanced performance with innovative technologies. This paper gives an outline of the SFR CD & BOP project plan that is examined as Generation IV R&D. The project plan covers advanced in-service inspection and repair, improved steam generator more reliability, advanced energy conversion system for higher efficiency, and leak-before-break assessment. The total schedule of the project plan consists of three steps: a viability study of proposal concepts (till 2006), performance tests for detail design specification (till 2010) and demonstration of system performance (till 2015). The R&D activities are carried out with international cooperation between France, Japan, Republic of Korea, the United Kingdom and the United States in the framework of Generation IV International Forum under the supervision of its SFR steering committee.

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