Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs-Reference-Cited by-同舟云学术

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Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs

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

Author:

Park Hae Min,Lee Jong Hyuk,Choi Chiwoong,Ha Kwi-Seok,You Byung Hyun,Heo Jaeseok,Kim Kyung Doo,Bae Sung Won,Lee Seung Wook,Lee Dong Hyuk,Lee Sang Ik,Park Chan Eok,Chung Bub Dong,Seul Kwang Won

Funder

Korea Institute of Energy Technology Evaluation and Planning

Ministry of Trade, Industry and Energy

Publisher

Elsevier BV

Reference55 articles.

1. SBLOCA Safety Analysis Evaluation Methodology for APR1400 Type Nuclear Power Plants Using the SPACE Code, Topical Report,2013

2. Use of BE SYS-TH codes for licensing current status in France issues encountered by AREVA;The Forum & Network of System Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics (FONESYS),2017

3. “Emergency Core Cooling System Performance during Loss-Of-Coolant Accidents (LOCA)” and Associated Regulatory Guides,2016

4. Technical basis for the revision of ECCS acceptance criteria of domestic PWR plants;Lee;Korea Institute of Nuclear Safety,2017

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