Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel-Reference-Cited by-同舟云学术

Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel

Published:2022-08 Issue: Volume:150 Page:104298
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Saffari A.H.,Esmaili H.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference32 articles.

1. Thermal-hydraulic phenomena for water cooled nuclear reactors;Aksan;Nucl. Eng. Des.,2018

2. COBRA-EN: an Upgraded Version of the COBRA-3C/MIT Code for Thermal Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores;Basile,1999

3. Strategies for developing subchannel capability in an advanced system thermalhydraulic code: a literature review;Cheng;AECL Nucl. Rev.,2015

4. Design and analysis of 19 pin annular fuel rod cluster for pressure tube type boiling water reactor;Deokule;Nucl. Eng. Des.,2014

5. Reactor physics and thermal hydraulic Analysis of annular fuel rod cluster for Advanced Heavy Water Reactor;Deokule;Energy Proc.,2015

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. Numerical study on the effect of lateral vibration frequency on the flow and heat transfer characteristics inside annular fuel elements;Thermal Science and Engineering Progress;2024-05

2. An inter-channel mixing model based on the void distribution in a rod bundle;Progress in Nuclear Energy;2024-03

3. Experimental study on flow split and pressure drop characteristics in a 3 × 3 dual-cooled annular rod bundle;Annals of Nuclear Energy;2023-12

4. Numerical Study of the Flow and Heat Transfer Characteristics within an Annular Fuel Element Under Lateral Vibration Conditions;2023