Refine your search:     
Report No.
 - 
Search Results: Records 1-6 displayed on this page of 6
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Development of safety design criteria and safety design guidelines for Generation IV sodium-cooled fast reactors

Futagami, Satoshi; Kubo, Shigenobu; 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

Journal Articles

GIF risk and safety working group; Application of the ISAM methodology to Gen-IV nuclear systems

Okano, Yasushi; Ammirabile, L.*; Sofu, T.*

2018 GIF Symposium Proceedings (Internet), p.253 - 262, 2020/05

GIF ISAM (Integrated Safety Assessment Methodology) includes five analytical tools (i.e. QSR, PIRT, OPT, DPA, PSA) and it is intended that each tool be used to answer specific safety-related questions with different levels of detail during various design stages and the ISAM as a whole offers flexibility and a graded approach to analyse technical issues of complex system architectures. Although each tool can be selected for individual and exclusive use, the full value of the integrated methodology is derived from using all tools, in an iterative fashion and in combination with the others, throughout the design process. The paper describes what is ISAM and pilot examples of individual use of QSR, PIRT and OPT and also combination application of DPA-PSA.

Journal Articles

The Safety design criteria development and summary of its update for the Generation-IV SFR systems

Sofu, T.*; Okano, Yasushi

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 8 Pages, 2017/06

The Generation-IV International Forum (GIF) completed development of Safety Design Criteria (SDC) for the Generation-IV SFR systems in May, 2013. SDC reflects the high-level GIF safety and reliability goals and follows GIF basic safety approach. It aims to establish reference criteria for safety design of structures, systems and components and achieve harmonization of safety approaches among GIF member states. Following its public release, SDC report was distributed to international organizations and national regulatory bodies for review and feedback. Based on comments received during the following two-year period, SDC report underwent a revision reflecting feedback received from IAEA, NRC (USA), IRSN (France), and NNSA (China). This paper provides an overview of SDC development effort, and summarizes its revisions based the comments/suggestions received from the international review.

Journal Articles

Safety design criteria for generation IV sodium-cooled fast reactor system

Nakai, Ryodai; Sofu, T.*

GIF Symposium Proceedings/2012 Annual Report of NEA, No.7141, p.35 - 43, 2013/00

Oral presentation

Development of safety design guideline on structures, systems and components for Generation IV sodium-cooled fast reactors

Futagami, Satoshi; Kubo, Shigenobu; Sofu, T.*

no journal, , 

no abstracts in English

Oral presentation

Development of SDC and SDG for Generation IV Sodium-cooled Fast Reactors

Futagami, Satoshi; Kubo, Shigenobu; Sofu, T.*

no journal, , 

no abstracts in English

6 (Records 1-6 displayed on this page)
  • 1