Nonlinear numerical study of crack initiation and propagation in a reactor pressure vessel under pressurized thermal shock using XFEM-Reference-Cited by-同舟云学术

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Nonlinear numerical study of crack initiation and propagation in a reactor pressure vessel under pressurized thermal shock using XFEM

Published:2017-08-10 Issue:2 Volume:41 Page:374-386
ISSN:8756-758X
Container-title:Fatigue & Fracture of Engineering Materials & Structures
language:en
Short-container-title:Fatigue Fract Eng Mater Struct

Author:

Sun X.¹,Chai G.¹^ORCID,Bao Y.¹

Affiliation:

1. Key Laboratory of E&M; Zhejiang University of Technology, Ministry of Education and Zhejiang Province; Hangzhou 310014 China

Funder

National Natural Science Foundation of China

Publisher

Wiley

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Link

http://onlinelibrary.wiley.com/wol1/doi/10.1111/ffe.12689/fullpdf

Reference30 articles.

1. Failure assessment of RPV nozzle under loss of coolant accident;Siegele;Nucl. Eng. Des.,1999

2. Effect of the bainitic and martensitic microstructures on the hardening and embrittlement under neutron irradiation of a reactor pressure vessel steel;Marini;J. Nucl. Mater.,2015

3. A constraint-equivalent approach for assessing fracture toughness of RPV steels under neutron irradiation;Chen;Nucl. Eng. Des.,2012

4. Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading;Chen;Nucl. Eng. Des.,2014

5. Importance of fracture criterion and crack tip material characterization in probabilistic fracture mechanics analysis of an RPV under a pressurized thermal shock;Shibata;Int. J. Press. Vess. Pip.,2004

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1. Evaluation of RPV closure head penetration integrity considering fitting and residual stresses;Nuclear Engineering and Design;2024-08

2. Fracture studies on reactor pressure vessel subjected to pressurised thermal shock: A review;Nuclear Engineering and Design;2020-04

3. Thickness effects of base wall and inlet pipe on the structural integrity of reactor pressure vessels considering ductile-to-brittle transition;Engineering Failure Analysis;2019-11

4. Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel;Fatigue & Fracture of Engineering Materials & Structures;2018-03-12

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