Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach-Reference-Cited by-同舟云学术

Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach

Published:2020-10 Issue: Volume:238 Page:107258
ISSN:0013-7944
Container-title:Engineering Fracture Mechanics
language:en
Short-container-title:Engineering Fracture Mechanics

Author:

Mora D.F.,Costa Garrido O.,Mukin R.,Niffenegger M.

Funder

PROBAB

PROACTIV

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference42 articles.

1. The evolution of mechanical property change in irradiated austenitic stainless steels;Lucas;J Nucl Mater,1993

2. Integrity of reactor pressure vessels in nuclear power plants: assessment of irradiation Embrittlement effects in reactor pressure vessel steels. Vienna: International Atomic Energy Agency; 2009.

3. Effects of embedded cracks and residual stresses on the integrity of a reactor pressure vessel;Qian;Eng Fail Anal,2018

4. In-plane and out-of-plane constraint effects under pressurized thermal shocks;Qian;Int J Solids Struct,2014

5. Effect of non-uniform reactor cooling on fracture and constraint of a reactor pressure vessel;Qian;Fatigue Fract Eng Mater Struct,2018

Cited by 7 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Fatigue crack growth simulation by extended finite element method: A review of case studies;Fatigue & Fracture of Engineering Materials & Structures;2024-04-10

2. A study on XFEM simulation of tensile, fracture toughness, and fatigue crack growth behavior of Al 2024 alloy through fatigue crack growth rate models using genetic algorithm;Fatigue & Fracture of Engineering Materials & Structures;2023-03-16

3. Remarkable embrittlement and its origins in quenched reactor pressure vessel steels;Journal of Nuclear Materials;2022-07

4. Micromechanical Modeling of Corroded Steel Joints under Excessive Plastic Deformations;Journal of Performance of Constructed Facilities;2022-04

5. Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System;Science and Technology of Nuclear Installations;2022-02-02