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Material Strength Evaluation for 60 Years Design in Japanese Sodium Fast Reactor

[+] Author Affiliations
Yuji Nagae, Takashi Onizawa, Shigeru Takaya, Takuya Yamashita

Japan Atomic Energy Agency, O-arai, Ibaraki, Japan

Paper No. PVP2014-28689, pp. V001T01A063; 9 pages
doi:10.1115/PVP2014-28689
From:
  • ASME 2014 Pressure Vessels and Piping Conference
  • Volume 1: Codes and Standards
  • Anaheim, California, USA, July 20–24, 2014
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-4598-1
  • Copyright © 2014 by ASME

abstract

316FR and Mod.9Cr-1Mo steels are candidates as structural materials for Japanese Sodium Fast Reactor (JSFR). The design life and operation temperature of JSFR is 60 years and 550 °C, respectively. Time-dependent allowable stress is essential. The evaluation of allowable stresses to 500,000 h is a considerable item. Long term strength is evaluated from a viewpoint of microstructural evaluation related to fracture mechanism. In addition, degradation after long term operation at elevated temperature is important. Aging is considered as one of the degradation. The effect of aging on short term property is analyzed. Material strength standard is also necessary for very thick tube sheets of forgings and small diameter thin walled seamless pipes, which are made of Mod.9Cr-1Mo steel in steam generators. This paper summarized currently available data and information on the above items, and shows path forward to the development of material strength standard for 60 years design in JSFR.

Copyright © 2014 by ASME

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