Evaluation of impact properties of weld joint of reactor pressure vessel steels with the use of miniaturized specimens-Reference-Cited by-同舟云学术

Evaluation of impact properties of weld joint of reactor pressure vessel steels with the use of miniaturized specimens

Published:2012-06 Issue:6 Volume:49 Page:618-631
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Kim Byung Jun,Mitsui Hideaki,Kasada Ryuta,Kimura Akihiko

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/00223131.2012.687235

Reference21 articles.

1. Effect of specimen size on the impact properties of neutron irradiated A533B steel

2. Kimura, A., Suzuki, T., Jincho, M. and Matsui, H. 1998.Dependence of ductile–brittle transition behavior on the sizes of Charpy specimen and the location of V-notch in the HAZ of welded A533B PVS, 110–122. Small Specimen Test Technique, ASTM STP 1329.

3. Notch position in the HAZ specimen of reactor pressure vessel steel

4. Effects of notch position of the Charpy impact specimen on the failure behavior in heat affected zone

5. Residual stress relief and local embrittlement in a A533B reactor pressure vessel weldment

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