This paper discusses about the activities for codification of new structural materials in the Japan Atomic Energy Agency (JAEA) for the Japanese demonstration fast breeder reactor (Hereafter, DFBR), of which operation is presumed to be around 2025. 316FR is to be used for a reactor vessel and internals and Mod.9Cr-1Mo (ASME Gr.91) steel is to be used for primary and secondary coolant circuits, including intermediate heat exchangers and steam generators. 316FR was developed in Japan by optimizing chemical composition within the specifications of SUS316 in the Japanese Industrial Standard which is equivalent to Type 316 stainless steel. The optimization was performed from the viewpoint of maximizing the creep resistance under fast breeder conditions. Mod.9Cr-1Mo steel was developed in Oakridge National Laboratory in the United States. 316FR has not been registered in current codes and standards. Mod.9Cr-1Mo steel is codified in ASTM/ASME, but it has not been registered in current Japanese nuclear codes and standards either. Therefore, it is necessary to include the materials in Japan Society of Mechanical Engineers Design and Construction Code- Part II Fast Breeder Reactors- (Hereafter, JSME FBR Code). Research and development on the two materials were conducted on 1990’s and the result has been summarized as a part of “Draft Demonstration Reactor Design Standard (Hereafter, DDS)”. However, DDS cannot be used for the DFBR as it is for the following reasons. (1)The design life targeted in DDS was 40 years. But the design life of the DFBR is 60 years. (2) Mod.9Cr-1Mo steel was to be used for only steam generators. (3)The design of the DFBR has various innovative features such as compact and simple reactor block, very short piping systems, double-wall-straight tube steam generators and so on. This paper summarized currently available data and information on the above items and shows path forward to the development of a material strength standard for DFBR.
Skip Nav Destination
ASME 2009 Pressure Vessels and Piping Conference
July 26–30, 2009
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping
ISBN:
978-0-7918-4364-2
PROCEEDINGS PAPER
Development of a Material Strength Standard for Japanese Demonstration Fast Breeder Reactor
Takashi Onizawa,
Takashi Onizawa
Japan Atomic Energy Agency, Ibaraki, Japan
Search for other works by this author on:
Yuji Nagae,
Yuji Nagae
Japan Atomic Energy Agency, Ibaraki, Japan
Search for other works by this author on:
Takashi Wakai,
Takashi Wakai
Japan Atomic Energy Agancy, Ibaraki, Japan
Search for other works by this author on:
Tai Asayama
Tai Asayama
Japan Atomic Energy Agency, Ibaraki, Japan
Search for other works by this author on:
Takashi Onizawa
Japan Atomic Energy Agency, Ibaraki, Japan
Yuji Nagae
Japan Atomic Energy Agency, Ibaraki, Japan
Takashi Wakai
Japan Atomic Energy Agancy, Ibaraki, Japan
Tai Asayama
Japan Atomic Energy Agency, Ibaraki, Japan
Paper No:
PVP2009-77984, pp. 727-734; 8 pages
Published Online:
July 9, 2010
Citation
Onizawa, T, Nagae, Y, Wakai, T, & Asayama, T. "Development of a Material Strength Standard for Japanese Demonstration Fast Breeder Reactor." Proceedings of the ASME 2009 Pressure Vessels and Piping Conference. Volume 1: Codes and Standards. Prague, Czech Republic. July 26–30, 2009. pp. 727-734. ASME. https://doi.org/10.1115/PVP2009-77984
Download citation file:
14
Views
Related Proceedings Papers
Related Articles
Overview of Creep Strength and Oxidation of Heat-Resistant Alloy Sheets and Foils for Compact Heat Exchangers
J. Turbomach (October,2006)
Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors
J. Pressure Vessel Technol (February,2001)
Heat Exchanger Design Considerations for Gas Turbine HTGR Power Plant
J. Eng. Power (April,1977)
Related Chapters
Design of Indian Pressurized Heavy Water Reactors
Global Applications of the ASME Boiler & Pressure Vessel Code
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition