原子炉格納容器鋼材の局部破損の限界条件（切欠き付平板試験片及び実厚相当試験体の引張試験）-Reference-Cited by-同舟云学术

原子炉格納容器鋼材の局部破損の限界条件（切欠き付平板試験片及び実厚相当試験体の引張試験）

Published:2023 Issue:924 Volume:89 Page:23-00070-23-00070
ISSN:2187-9761
Container-title:Transactions of the JSME (in Japanese)
language:en
Short-container-title:

Author:

NAKAMURA Hitoshi¹,ARAI Kensaku²,KIKUCHI Masaaki²

Affiliation:

1. Center for creation of symbiosis society with risk, Yokohama National University

2. Nuclear Regulation Authority

Publisher

Japan Society of Mechanical Engineers

Subject

General Medicine

Link

https://www.jstage.jst.go.jp/article/transjsme/89/924/89_23-00070/_pdf

Reference18 articles.

1. An Gyu-back,Yoshida Satoshi, Ohata Mitsuru and Toyoda Masao, Strength mismatch effect on ductile crack initiation from notch root of structural steel, Journal of the Society of Naval Architects of Japan, Vol. 2001, No. 190, pp. 579-590 (in Japanese).

2. Arai Kensaku, Nakamura Hitoshi and Kikuchi Masaaki, Study on local failure conditions of nuclear containment steels(Tensile tests for notched round-bar specimens of welds and plate specimens of base metals), JSME M&M2021 Material mechanics conference (2021), DOI: 10.1299/jsmemm.2021.OS1906 (in Japanese).

3. ASME Boiler & Pressure Vessel Code, Section VIII, Division 2 Alternative Rules, Article 5.3, Protection against local failure, The American Society of Mechanical Engineers (2007).

4. Bridgman P. W., Studies in Large Plastic Flow and Fracture. (1952) pp. 9-37, McGraw-Hill.

5. Enami Keitaro and Nagai Kotobu, Evaluation of Plastic Deformation Limit by Circumferentially Notched Tension Test, Tesu-to-Hagane, Vol. 91, No. 2 (2005), pp.285-291.