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Journal Articles

Activities of the GIF safety and operation project of sodium-cooled fast reactor systems

Yamano, Hidemasa; Vasile, A.*; Kang, S.-H.*; Summer, T.*; Tsige-Tamirat, H.*; Wang, J.*; Ashurko, I.*

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 7 Pages, 2019/05

The Generation IV (GEN-IV) international forum is a framework for international co-operation in research and development for the next generation of nuclear energy systems. Within the GEN-IV sodium-cooled fast reactor (SFR) system arrangement, the SFR Safety and Operation (SO) project addresses the areas of safety technology and reactor operation technology developments. The aims of the SO project include (1) analyses and experiments that support establishing safety approaches and validating performance of specific safety features, (2) development and verification of computational tools and validation of models employed in safety assessment and facility licensing, and (3) acquisition of reactor operation technology, as determined largely from experience and testing in operating SFR plants. The tasks in the SO topics are categorized into the following three work packages (WP): WP-SO-1 "Methods, Models and Codes", WP-SO-2 "Experimental Programs and Operational Experience", and WP-SO-3 "Studies of Innovative Design and Safety Systems". This paper reports recent activities within the SO project.

Journal Articles

Current status of GIF collaborations on sodium-cooled fast reactor system

Hayafune, Hiroki; Glatz, J.-P.*; Yang, H.*; Ruggieri, J.-M.*; Kim, Y.-I.*; Ashurko, Y.*; Hill, R.*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 12 Pages, 2017/06

The SFR system arrangement Phase II became effective on 16 February 2016 by signatures of CEA, JAEA, KAERI, USDOE, and Rosatom, and was extended for additional 10 years. Collaboration of GIF SFR is growing adding new reactor concepts and related RDs. In 2015, a project arrangement on SFR System Integration and Assessment (SIA) has been signed by 7 members : China, EU, France, Japan, Korea, Russia and US. In the SIA project, RD needs from the SFR design will be shown to the RD project, and RD results from each RD project will be integrated into the designs.

Journal Articles

Recent activities of the safety and operation project of the sodium-cooled fast reactor in the Generation IV International Forum

Vasile, A.*; Ren, L.*; Fanning, T.*; Tsige-Tamirat, H.*; Yamano, Hidemasa; Kang, S.-H.*; Ashurko, I.*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 15 Pages, 2017/06

The tasks in the Safety and Operation (SO) topics are categorized into the following three work packages (WP): WP-SO-1 Methods, Models and codes is devoted to the development of tools for the evaluation of safety, WP-SO-2 Experimental Programs and Operational Experiences includes the operation, maintenance and testing experiences in experimental facilities and SFRs (e.g., Monju, Phenix, BN-600 and CEFR), and WP-SO-3 Studies of Innovative Design and Safety Systems relates to safety technologies for GEN-IV reactors such as active and passive safety systems and other specific design features. In this paper, recent activities in the SO project are described.

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:99 Percentile:99.52(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

Results of studies on safety of the BN-600 reactor with hybrid core for the purpose of weapons Pu disposition

Kuznetsov, I.*; Shvetsov, Y. E.*; Ashurko, Yu. M.*; Volkov, A. V.*; Kashcheev, M. V.*; Tsykunov, A. G.*; Kamanin, Y. L.*; Bakhmetyev, A. M.*; Zamyatin, V. A.*; Niwa, Hajime; et al.

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

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