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Development of High Chromium Steel for SFR in Japan and Creep-Fatigue Assessment of the Welded Joint

[+] Author Affiliations
Takashi Wakai

Japan Atomic Energy Agancy, Ibaraki, Japan

Nobuhiro Isobe

Hitachi, Ltd., Ibaraki, Japan

Shingo Date

Mitsubishi Heavy Industry, Hyogo, Japan

Tai Asayama

Japan Atomic Energy Agency, Ibaraki, Japan

Shigenobu Kubo

Japan Atomic Power Company, Tokyo, Japan

Paper No. PVP2008-61359, pp. 711-718; 8 pages
doi:10.1115/PVP2008-61359
From:
  • ASME 2008 Pressure Vessels and Piping Conference
  • Volume 1: Codes and Standards
  • Chicago, Illinois, USA, July 27–31, 2008
  • Conference Sponsors: Pressure Vessels and Piping
  • ISBN: 978-0-7918-4824-1 | eISBN: 0-7918-3828-5
  • Copyright © 2008 by ASME

abstract

This paper describes the provisional material specifications of the high chromium (Cr) ferritic steel for the Sodium cooled Fast Reactor (SFR) and development of creep-fatigue assessment procedure for the welded joint made of the steel. Based on the test results, it was revealed that tungsten (W) should be diminished to achieve better creep-fatigue strength and toughness after long term aging at elevated temperature. Metallurgical examinations using a scanning electron microscope showed that W precipitated on the grain boundaries as “Laves phase” during aging process. The toughness of the steel which contained much W might be degraded by such coarse precipitations on the grain boundaries. As a result, provisional specifications of the high Cr ferritic steel for SFR pipes and tubes were proposed. Creep-fatigue strength assessment procedure for the welded joints made of the steels was also investigated. An assessment procedure using 2-element model was proposed and verified by comparing with some creep-fatigue test results. The creep-fatigue lives observed in the experiments were well predicted by the proposed assessment procedure, but the failure of the welded joints really occurred in the heat affected zone (HAZ) in some creep-fatigue tests. Since the HAZ was not taken into account in the procedure, there were obviously some rooms for improvement. Creep-fatigue failure mechanisms of the welded joint must be investigated and the characteristics of the HAZ must be formulated for more precise creep-fatigue strength assessment.

Copyright © 2008 by ASME

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