Investigation of nuclear reactor core thermal-hydraulic characteristics after partial loss of flow accident-Reference-Cited by-同舟云学术

Investigation of nuclear reactor core thermal-hydraulic characteristics after partial loss of flow accident

Published:2023-06 Issue: Volume:174 Page:637-662
ISSN:0957-5820
Container-title:Process Safety and Environmental Protection
language:en
Short-container-title:Process Safety and Environmental Protection

Author:

dizaji Davod Naghavi,Ghafari Mohsen,Vosoughi Naser

Publisher

Elsevier BV

Subject

Safety, Risk, Reliability and Quality,General Chemical Engineering,Environmental Chemistry,Environmental Engineering

Reference41 articles.

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4. Considerations in relation to off-site emergency procedures and response for nuclear accidents;Ashley;Process Saf. Environ. Prot.,2017

5. Phenomenological investigations on the turbulent flow structures in a rod bundle array with mixing devices;Chang;Nucl. Eng. Des.,2008

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