Thermal-Hydraulic Transient Analyses for Primary Coolant System of HFRR Using RELAP5
Author:
Affiliation:
1. Bhabha Atomic Research Centre, Research Reactor Design & Projects Division, Trombay, Mumbai, India
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295450.2022.2156245
Reference9 articles.
1. Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor
2. “PSAR Part-A of HFRR, ‘Primary Coolant System,’” RRDPD, BARC (2018).
3. Mixing of hot and cold fluid inside a square chimney model for a pool type research reactor – An experimental study
4. RELAP5 DEVELOPMENT TEAM, “RELAP5/MOD3 Code Manual,” NUREG/CR-5535, U.S. Nuclear Regulatory Commission.
5. The Determination of Forced-Convection Surface-Boiling Heat Transfer
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