In the structural design of fast breeder reactors, irradiation effects and sodium environmental effects on structural materials have to be taken into account. In this paper, firstly, an evaluation procedure for irradiation effects on the mechanical properties of 316FR (FBR Grade 316 stainless steel), which is a newly developed stainless steel for the Japanese demonstration fast breeder reactor, is proposed. The procedure gives a limit of accumulated fast neutron fluence as a function of temperature, so that the minimum tensile fracture elongation of 10 percent, which is the threshold for material to stay ductile, is maintained. Furthermore, the procedure determined a creep life reduction factor and a creep rate increase factor as a function of accumulated thermal neutron fluence within the limitation of the accumulated fast neutron fluence, to account for the creep life reduction and the increase of creep rate due to irradiation. Secondly, an evaluation procedure for sodium environmental effects on the integrity of 316FR and modified 9Cr-1Mo steel was proposed. It gave a corrosion allowance as a function of temperature, oxygen content, and service time, based on corrosion tests. It determined that no correction factors that correspond to sodium environment on design allowable stresses, etc., are needed, because no adverse effects of sodium on the mechanical properties of 316FR and modified 9Cr-1Mo steel were to be expected in the service conditions of FBRs. Both the procedures have been incorporated into the Japanese Elevated Temperature Structural Design Guide for Demonstration Fast Breeder Reactor.
Skip Nav Destination
e-mail: asayama@oec.jnc.go.jp
Article navigation
February 2001
Technical Papers
Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors
Tai Asayama,
e-mail: asayama@oec.jnc.go.jp
Tai Asayama
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Search for other works by this author on:
Yasuhiro Abe,
Yasuhiro Abe
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Search for other works by this author on:
Noriko Miyaji,
Noriko Miyaji
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Search for other works by this author on:
Mamoru Koi,
Mamoru Koi
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Search for other works by this author on:
Tomohiro Furukawa,
Tomohiro Furukawa
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Search for other works by this author on:
Eiichi Yoshida
Eiichi Yoshida
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Search for other works by this author on:
Tai Asayama
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
e-mail: asayama@oec.jnc.go.jp
Yasuhiro Abe
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Noriko Miyaji
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Mamoru Koi
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Tomohiro Furukawa
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Eiichi Yoshida
Oarai Engineering Center, Japan Nuclear Cycle Development Institute, Ibaraki, Japan
Contributed by the Pressure Vessels and Piping Division and presented at the Pressure Vessels and Piping Conference, Boston, Massachusetts, August 1–5, 1999, of THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS. Manuscript received by the PVP Division, October 18, 1999; revised manuscript received October 27, 2000. Editor: S. Y. Zamrik.
J. Pressure Vessel Technol. Feb 2001, 123(1): 49-57 (9 pages)
Published Online: October 27, 2000
Article history
Received:
October 18, 1999
Revised:
October 27, 2000
Citation
Asayama, T., Abe , Y., Miyaji , N., Koi , M., Furukawa , T., and Yoshida, E. (October 27, 2000). "Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors ." ASME. J. Pressure Vessel Technol. February 2001; 123(1): 49–57. https://doi.org/10.1115/1.1338119
Download citation file:
Get Email Alerts
Surface Strain Measurement for Non-Intrusive Internal Pressure Evaluation of a Cannon
J. Pressure Vessel Technol (December 2024)
Dynamic Response and Damage Analysis of a Large Steel Tank Impacted by an Explosive Fragment
J. Pressure Vessel Technol (February 2025)
Related Articles
Elevated-Temperature Mechanical Properties of an Advanced-Type 316 Stainless Steel
J. Pressure Vessel Technol (February,2001)
Radiation Effects in Boiling Water Reactor Pressure Vessel Steels
J. Eng. Mater. Technol (April,1980)
Mechanical Properties of Roll Extruded Nuclear Reactor Piping
J. Pressure Vessel Technol (May,1976)
Irradiation Effects on the Behavior of Structural Materials at Elevated Temperature
J. Eng. Mater. Technol (April,1978)
Related Chapters
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
A Study of Irradiation-Induced Growth of Modified and Advanced Zr-Nb System Alloys after Irradiation in the VVER-1000 Reactor Core at Temelin NPP
Zirconium in the Nuclear Industry: 20th International Symposium
Long.Term Reactivity Change and Control: On.Power Refuelling
Fundamentals of CANDU Reactor Physics