Numerical analysis of the BWR-5 beltline region containing a crack postulated for an extended period of operation

Author:

Montejo Salatiel Pérez,López Pablo Ruiz,Mendoza Gilberto Soto,Molina Alejandra Armenta,García Abraham Villanueva,Gómez Luis H. Hernández

Publisher

Elsevier BV

Subject

General Engineering,Energy Engineering and Power Technology

Reference17 articles.

1. Section III, Division 1 Subsection NB. Rules for Construction of Nuclear Facility Components;American Society of Mechanical Engineers,2007

2. Section XI. Rules for Inservice Inspection of Nuclear Power Plant Components;American Society of Mechanical Engineers,2007

3. ANSYS Mechanical Tutorials, (2017) Customer Training Material. pp. 113-119. Recovered from https://support.ansys.com/portal/site/AnsysCustomerPortal.

4. A. Zahoor, (1990) Ductile Fracture Handbook, Vol. 3, Electric Power Research Institute Report NP-6301, USA: EPRI, pp. 8.1-1.

5. Lineal Elastic Fracture Mechanics Analysis Applied for the Evaluation of the Structural Integrity of a Boiling Water Reactor Vessel Considering Neutronic Irradiation.;Alvarez-Loya;Defect and Diffusion Forum,2019

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1. Accumulated Damage of the Main Steam Nozzle of a BWR-5;Advanced Structured Materials;2023

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