Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Development of a human reliability analysis framework for nominal human error probability estimate of the TRIGA research reactor in Thailand

  • Wasin Vechgama (Korea Atomic Energy Research Institute) ;
  • Jinkyun Park (Korea Atomic Energy Research Institute) ;
  • Saensuk Wetchagarun (Thailand Institute of Nuclear Technology (Public Organization)) ;
  • Anantachai Pechrak (Thailand Institute of Nuclear Technology (Public Organization)) ;
  • Kampanart Silva (National Energy Technology Center, National Science and Technology Development Agency)
  • Received : 2024.03.18
  • Accepted : 2024.06.15
  • Published : 2024.11.25
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Abstract

Human reliability analysis (HRA) of nuclear research reactors often encounters a lack of human performance data, a challenge that is also faced by the TRIGA reactor of Thailand having no specific full method or human error database for HRA. To overcome this challenge, in 2023, HRA teams from the Korea Atomic Energy Research Institute (KAERI) and the Thailand Institute of Nuclear Technology (TINT) jointly developed an HRA framework for the TRIGA reactor. In the HRA framework development, the HRA practitioners applied KAERI's three main HRA tools, namely 1) the EMpirical data-Based crew Reliability Assessment and Cognitive Error analysis (EMBRACE) method, 2) the Human Reliability data EXtraction (HuREX) database, and 3) the TAsk COMplexity (TACOM) method. The HRA framework covers the overall process including the classification of documents and human error types as well as nominal human error extraction for estimating nominal human error probabilities. According to the results of the first use of the HRA framework on the TRIGA reactor in Thailand, the HRA framework provided an effective way to improve the procedures and systematically identify nominal human errors of actions in the emergency procedures.

Keywords

Acknowledgement

This work was supported by a grant from the Nuclear Safety Research Program from the Korea Foundation of Nuclear Safety (KOFONS), funded by the Nuclear Safety and Security Commission of the Republic of Korea (No. RS-2021-KN052610). Also, the authors thank the Korea Atomic Energy Research Institute (KAERI), Korea National University of Science and Technology (UST), and Thailand Institute of Nuclear Technology (TINT) for the opportunity and resources for conducting this project.

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