Hydraulic benchmark data for PWR mixing vane grid-Reference-Cited by-同舟云学术

Hydraulic benchmark data for PWR mixing vane grid

Published:2013-11 Issue: Volume:264 Page:97-102
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Conner Michael E.,Hassan Yassin A.,Dominguez-Ontiveros Elvis E.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference9 articles.

1. CFD methodology and validation for single-phase flow in PWR fuel assemblies;Conner;Nuclear Engineering and Design,2010

2. Experimental benchmark data for PWR rod bundle with spacer-grids;Dominguez-Ontiveros,2010

3. The effect of support grid features on local, single-phase heat transfer measurements in rod bundles;Holloway;ASME Journal of Heat Transfer,2004

4. The effect of support grid design on azimuthal variation in heat transfer coefficient for rod bundles;Holloway;ASME Journal of Heat Transfer,2005

5. Single-phase convective heat transfer in rod bundles;Holloway;Nuclear Engineering and Design,2008

Cited by 51 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. Numerical study of mixing vane spacer grid effect on subchannel mixing in a 5 × 5 rod bundle;Annals of Nuclear Energy;2024-06

2. Review of spacer grid to rod fretting in pressurized water reactor;Nuclear Engineering and Design;2024-03

3. Large eddy simulation of a turbulent flow in a 5 x 5 rod bundle with a mixing vane spacer grid;Frontiers in Energy Research;2024-02-02

4. Development of supporting platform for the fine flow characteristics of reactor core;Nuclear Engineering and Technology;2023-12

5. Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures;Journal of Nuclear Materials;2023-12