Validation of fracture toughness characteristics of nuclear plant piping and safety margin analysis by using CP specimen-Reference-Cited by-同舟云学术

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Validation of fracture toughness characteristics of nuclear plant piping and safety margin analysis by using CP specimen

Published:2017-12 Issue: Volume:186 Page:39-46
ISSN:0013-7944
Container-title:Engineering Fracture Mechanics
language:en
Short-container-title:Engineering Fracture Mechanics

Author:

Park Soo,Shen Tao,Koo Jae-Mean,Seok Chang-Sung

Funder

National Research Foundation of Korea

Korea government

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference32 articles.

1. New engineering method of non-linear fracture mechanics analysis of circumferential through-wall cracked pipes;Huh,2000

2. ASME. ASME boiler and pressure vessel code section III;1996.

3. ASME, Rule for In-service inspection of nuclear power plant component - ASME boiler and pressure vessel code section XI.;1996.

4. ANSI/ANS. American National Standard. B31.1; 1996.

5. USNRC. Water hammer in nuclear power plant. NUREG-0582;1979.

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