Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor-Reference-Cited by-同舟云学术

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Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor

Published:2024-08 Issue: Volume:424 Page:113235
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Bhowmik P.K.,Sabharwall P.,Johnson J.T.,Retamales M.E.T.,Wang C.,O'Brien J.E.,Lietwiler C.,Wu Q.

Funder

US Department of Energy Office of Nuclear Energy

Publisher

Elsevier BV

Reference94 articles.

1. Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors;Abdellatif;Nucl. Eng. Technol.,2024

2. Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review;Abdellatif;Prog. Nucl. Energy,2024

3. Flow Instabilities in boiling channels and their suppression methodologies—A review;Abdellatif;Nucl. Eng. Des.,2024

4. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; Part I: SETs, and ITFs of PWRs, BWRs;Aksan;Vvers. Nucl. Eng. Des.,2019

5. Hydraulic performance and flow resistance tests of various hydraulic parts for optimal design of a reactor coolant pump for a small modular reactor;Bae;Nucl. Eng. Technol.,2023

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