Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility-Reference-Cited by-同舟云学术

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Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility

Published:2024-08 Issue:8 Volume:56 Page:2893-2905
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Al-Yahia Omar S.^ORCID,Clifford Ivor,Ferroukhi Hakim

Funder

Horizon 2020 Euratom

ENSI

Publisher

Elsevier BV

Reference34 articles.

1. Safety of Nuclear Power Plants: Design, Specific Safety Requirement No. SSR-2/1 (Rev. 1,2016

2. Fukushima Daiichi Accident Study: Status as of April 2012;Gauntt,2012

3. Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete station blackout and long-term natural convection mode using the RELAP5/3.2 code;Hedayat;Nucl. Eng. Technol.,2017

4. Experimental research progress on passive safety systems of Chinese advanced PWR;Zejun;Nucl. Eng. Des.,2003

5. Thermal hydraulic calculation in a passive residual heat removal system of the SMART-P plant for forced and natural convection conditions;Chung;Nucl. Eng. Des.,2004

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Assessment of neptune_cfd applied to the study of a passive safety condenser: Modeling and first validation elements;Nuclear Engineering and Design;2024-08

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