J-R fracture properties of SA508-1a ferritic steels and SA312-TP347 austenitic steels for pressurized water reactor’s (PWR) primary coolant piping-Reference-Cited by-同舟云学术

J-R fracture properties of SA508-1a ferritic steels and SA312-TP347 austenitic steels for pressurized water reactor’s (PWR) primary coolant piping

Published:2000-06 Issue:1-2 Volume:199 Page:113-123
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lee B.S.,Oh Y.J.,Yoon J.H.,Kuk I.H.,Hong J.H.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference13 articles.

1. Ahn, Y.S., Kim, H.D., Byun, T.S., Kim, G.M., Hong, J.H., 1998. Application of intercritical heat treatment to improve toughness of SA508 Gr.3 reactor pressure vessel steel. Nucl. Eng. Des. (submitted.)

2. Instabilities in stabilized austenitic stainless steels;Ayer;Metall. Trans. A.,1992

3. Hackett, E.M., Kirk, M.T., Hays, R.A., 1986. An evaluation of J-R curve testing of nuclear piping materials using the direct current potential drop technique. In: US NRC Report, David Taylor Naval Ship Research and Development Center, NUREG/CR-4540, Annapolis, August 1986.

4. Hong, J.H., et al., 1991. J-R curve characteristics of primary piping materials for Yonggwang 3/4. In: Report KAERI/RM-21/91, Korea Atomic Energy Research Institute, March 1991.

5. Hong, J.H., et al., 1997. J-R characteristics of RCS surgeline pipe material for Yonggwang Unit 5/6. In: Report KAERI/CR-031/97, Korea Atomic Energy Research Institute, March 1997.

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