Development of Safety Design Criteria for the Lead-cooled Fast Reactor
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Authors
Alemberti, A.
Tucek, K.
Takahashi, M.
Obara, T.
Moiseev, A.
Tocheny, L.
Hwang, I.
Smith, C.
Wu, Y.
Zhou, T.
Subjects
Generation-IV International Forum (GIF)
Safety Design Criteria (SDC)
Lead Fast Reactor (LFR)
Safety Design Criteria (SDC)
Lead Fast Reactor (LFR)
Advisors
Date of Issue
2017
Date
Publisher
International Conference on Fast Reactors and Related Fuel Cycles
Language
Abstract
The Lead-cooled Fast Reactor (LFR) provisional System Steering Committee (pSSC) of the Generation-IV International Forum (GIF) has proposed a set of Safety Design Criteria (SDC) dedicated to LFRs. The objective of the LFR SDC is to prescribe a set of reference criteria for the design of LFR systems, structures, and components with the aim of achieving the safety goals of the Generation-IV reactor system. The LFR SDC has been derived from the already existing Safety Design Criteria for the Sodium-cooled Fast Reactor (SFR), since the GIF LFR and SFR systems share a number of characteristics, design features and some corresponding safety-related phenomenology. For the development of the LFR SDC it was also found useful to use the same structure and methodology of the GIF SFR SDC. A set of reference safety design criteria for LFRs is systematically and comprehensively laid out in the SDC to facilitate the development, safety assessment and licensing of LFRs, including BREST-OD-300, ALFRED, SSTAR, SVBR-100, CLEAR-I, and MYRRHA. The paper summarises results of the steps taken to draft the present set of LFR SDC and provides outlook for further review and development activities, in particular towards individual sets of detailed Safety Design Guidelines.
Type
Conference Paper
Description
Series/Report No
Department
Physics
Organization
Naval Postgraduate School (U.S.)
Identifiers
NPS Report Number
Sponsors
Naval Postgraduate School
Funding
Format
10 p.
Citation
Alemberti, A., Tuček, K., Takahashi, M., Obara, T., Moiseev, A., Tocheny, L., Hwang, I.S., Smith, C., Wu, Y., & Zhou, T. (2017). Development of Safety Design Criteria for the Lead-cooled Fast Reactor. International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17) Programme and Papers, (p. v). International Atomic Energy Agency (IAEA)
Distribution Statement
Rights
This publication is a work of the U.S. Government as defined in Title 17, United States Code, Section 101. Copyright protection is not available for this work in the United States.