Validation of a thermo-fluid-structure coupling approach for RPV creep failure analysis against FOREVER-EC2 experiment-Reference-Cited by-同舟云学术

Validation of a thermo-fluid-structure coupling approach for RPV creep failure analysis against FOREVER-EC2 experiment

Published:2019-11 Issue: Volume:133 Page:637-648
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Yu Peng,Ma Weimin,Villanueva Walter^ORCID,Karbojian Aram,Bechta Sevostian

Funder

APRI

ENSI

NKS

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference49 articles.

1. Altstadt, E., Willschuetz, H.-G., Sehgal, B.R., Weiss, F.-P., 2005. SARNET- Corium-WP10-2 Modelling of in-vessel retention after relocation of corium into the lower plenum, Technical Report FZR-437. October.

2. Extension of the ANSYS Creep and Damage Simulation Capabilities;Altstadt,2000

3. Introduction to ANSYS Fluent: Lecture 7 Turbulence Modelling;ANSYS,2016

4. Introduction to ANSYS Fluent: Lecture 9 Best Practice Guidelines;ANSYS;Fluent Tutorial Material.,2016

5. An experimental study of natural convection in a volumetrically heated spherical pool bounded on top with a rigid wall;Asfia;Nucl. Eng. Des.,1996

Cited by 4 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. Dynamic simulation of nozzle structure based on thermal-fluid-solid coupling analysis;Journal of Physics: Conference Series;2023-05-01

2. Development of a lumped-parameter code for efficient assessment of in-vessel melt retention strategy of LWRs;Progress in Nuclear Energy;2021-09

3. Establishment and analysis of thermo-fluid-solid coupling model of ink roller-ink under dynamic pressing contact;Journal of Mechanical Science and Technology;2021-06-29

4. Comparative analysis of reactor pressure vessel failure using two thermo-fluid-structure coupling approaches;Nuclear Engineering and Design;2020-11