Application of probabilistic safety assessment (PSA) to the power reactor innovative small module (PRISM)-Reference-Cited by-同舟云学术

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Application of probabilistic safety assessment (PSA) to the power reactor innovative small module (PRISM)

Published:2022-09 Issue:9 Volume:54 Page:3324-3335
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Alrammah Ibrahim^ORCID

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference39 articles.

1. A Methodology for Analyzing the consequences of Accidents in Sodium-Cooled Fast Reactors;Brunett,2010

2. Analysis of Transient Overpower Scenarios in sodium Fast Reactors;Grabaskas,2010

3. PRISM reference fuel design;Loewen;Nucl. Eng. Des.,2018

4. Integrated Fast Reactor;Pfeffer,2016

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1. Evaluating Risks of Multi-unit Nuclear Sites: Insights and Considerations;Arabian Journal for Science and Engineering;2023-12-26

2. Seismic resilience assessment of Small Modular Reactors by a Three-loop Monte Carlo Simulation;Nuclear Engineering and Design;2023-08

3. Analysis of nuclear accident scenarios and emergency planning zones for a proposed Advanced Power Reactor 1400 (APR1400);Nuclear Engineering and Design;2023-06

4. A digitalized framework for responding to radiological accidents in a public major event;Journal of Radiation Research and Applied Sciences;2023-06

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