Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR-Reference-Cited by-同舟云学术

Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR

Published:2021 Issue: Volume:3 Page:108-118
ISSN:2468-6050
Container-title:International Journal of Advanced Nuclear Reactor Design and Technology
language:en
Short-container-title:International Journal of Advanced Nuclear Reactor Design and Technology

Author:

Li Chenxi,Liao Haoyu,Wu Yingwei,Tian Wenxi,Su G.H.,Qiu Suizheng

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

General Medicine

Reference13 articles.

1. Cracked Pellet Gap Conductance Model: Comparison of Frap-S Calculations with Measured Fuel Centerline Temperatures. No. CONF-750360-2;MacDonald,1975

2. Annular fuel for high-power-density pressurized water reactors: motivation and overview;Hejzlar;Nucl. Technol.,2007

3. Development of a thermal-hydraulic analysis code for annular fuel assemblies;Han;Nucl. Eng. Des.,2003

4. Thermal hydraulic performance assessment of dual-cooled annular nuclear fuel for OPR-1000;Shin;Nucl. Eng. Des.,2012

5. Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs;Deng;Nucl. Eng. Des.,2016

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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. Experimental study on coupled quenching behavior in a dual-cooled annular rod channel;Progress in Nuclear Energy;2023-10

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

4. CAMPUS-ANNULAR: Preliminary multiphysics modeling of annular fuel performance under normal operating and accident conditions;Progress in Nuclear Energy;2022-11

5. The fouling and thermal hydraulic coupling study on the typical 5 × 5 rod bundle in PWRs;Progress in Nuclear Energy;2022-06