A theoretical model for determination of fracture toughness of reactor pressure vessel steels in the transition region from automated ball indentation test-Reference-Cited by-同舟云学术

A theoretical model for determination of fracture toughness of reactor pressure vessel steels in the transition region from automated ball indentation test

Published:1998-02 Issue:3 Volume:252 Page:187-194
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Byun Thak Sang,Kim Jin Weon,Hong Jun Hwa

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference31 articles.

1. F.M. Haggag, R.K. Nanstad, D.N. Braski, in: D.L. Mariott, T.R. Mager, W.H. Bamford (Eds.), Innovative Approaches to Irradiation Damage and Fracture Analysis, vol. 170, ASME PVP, 1989, pp. 101–107.

2. R.A. George, S. Dinda, A.S. Kasper, Met. Prog. (1976) 30.

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