Jooyoung Park

ORCID: 0000-0003-4211-0884
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About
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Research Areas
  • Risk and Safety Analysis
  • Occupational Health and Safety Research
  • Human-Automation Interaction and Safety
  • Graphite, nuclear technology, radiation studies
  • Reliability and Maintenance Optimization
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear and radioactivity studies
  • Infrastructure Resilience and Vulnerability Analysis
  • Technology Adoption and User Behaviour
  • Technology Assessment and Management
  • Fault Detection and Control Systems
  • Science Education and Pedagogy
  • Nuclear Materials and Properties
  • Systems Engineering Methodologies and Applications
  • Risk Perception and Management
  • Education, Safety, and Science Studies
  • Ergonomics and Human Factors
  • Education and Learning Interventions
  • Complex Systems and Decision Making
  • Quality and Safety in Healthcare
  • Intelligent Tutoring Systems and Adaptive Learning
  • Healthcare Technology and Patient Monitoring
  • Postcolonial and Cultural Literary Studies
  • Cognitive Science and Mapping
  • Traffic and Road Safety

Norwegian University of Science and Technology
2025

Idaho National Laboratory
2019-2024

Ulsan National Institute of Science and Technology
2022

Korea Hydro and Nuclear Power (Korea)
2021

Korea Electric Power Corporation (South Korea)
2021

Chosun University
2016-2020

Performance shaping factors (PSFs) in a human reliability analysis (HRA) are one that may influence performance task. Most currently applicable HRA methods for nuclear power plants (NPPs) use PSFs to highlight error contributors and adjust basic probabilities (HEPs) assume nominal conditions of NPPs. Thus far, the effects have been treated independently. However, many studies fields psychology revealed there be relationships between PSFs. Therefore, inter-relationships need studied better...

10.1016/j.net.2019.07.004 article EN cc-by-nc-nd Nuclear Engineering and Technology 2019-07-05

Data scarcity in human reliability analysis (HRA) has been a major challenge the quantification process. Many institutes have collected HRA data through experiments using full-scope simulators with actual operators. Nevertheless, there are still some limitations to relying solely on studies. This paper aims propose how collection studies can be supported Simplified Human Error Experimental Program (SHEEP). The SHEEP framework was developed by Idaho National Laboratory (INL) collect...

10.1016/j.ress.2022.108326 article EN cc-by-nc-nd Reliability Engineering & System Safety 2022-01-14

Abstract Recent advances in artificial intelligence (AI) have laid the foundation for developing a sophisticated collision avoidance system use maritime autonomous surface ships, potentially enhancing safety and decreasing navigator’s workload. Understanding reasoning behind an AI is inherently difficult. To help human operator understand what doing its reasoning, we employed human-centered design approach to develop transparency layers that visualize different aspects of operation by...

10.1007/s00773-024-01043-x article EN cc-by Journal of Marine Science and Technology 2025-01-06

Since the Fukushima Daiichi accident, there has been an emphasis on risk resulting from multi-unit accidents. Human reliability analysis (HRA) is one of important issues in probabilistic safety assessment (MUPSA). Hence, a need to properly identify all human and organizational factors relevant incident scenario nuclear power plant (NPP). This study identifies categorizes NPPs based review literature. These are then analyzed ascertain possible unit-to-unit interactions that be considered HRA...

10.1016/j.net.2018.08.022 article EN cc-by-nc-nd Nuclear Engineering and Technology 2018-09-07

Human-induced initiators (category-B actions) are the that caused by human errors and rarely explicitly identified modeled in probabilistic safety assessments (PSAs). The current concern over of multi-unit nuclear power sites is also a motivation for this research. This study proposes novel process identifying quantifying category-B actions ultimately, how to derive human-induced initiating event frequency scenario. Hence, fundamentally applies scenario–system–action search scheme using...

10.1080/00223131.2019.1661305 article EN Journal of Nuclear Science and Technology 2019-08-30

Many researchers have emphasized the importance of dynamic probabilistic safety assessment (PSA), which highlights necessity studies for human reliability analysis (HRA). Dynamic HRA concentrates on a account actions or how performance shaping factors (PSFs) can dynamically modify error probability (HEP) over time. In contrast, existing static does not consider as changes time event progressions. Accordingly, previous research conceptually suggested PSF lag and linger effects to treat...

10.1109/hsi47298.2019.8942621 article EN 2019-06-01

As an effort to support data collection for dynamic human reliability analysis (HRA), this study investigates time distributions task primitives defined in the Goals, Operators, Methods, and Selection rules (GOMS)–Human Reliability Analysis (HRA) method. GOMS-HRA was developed provide cognition-based error probability information HRA calculation Human Unimodel Nuclear Technology Enhance (HUNTER) framework. HUNTER is a framework modelling of conjunction with other tools. In paper, we...

10.54941/ahfe1004401 article EN AHFE international 2023-01-01

The Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER) is simulation software modeling the human portion of risk. HUNTER built on a framework that separately models individual, task, and environmental factors. As dynamic reliability analysis (HRA) method, it affords advantages over traditional static or worksheet-based HRA approaches, such as ability model what-if scenarios produce outputs beyond error probabilities. In this paper, validation was conducted task time...

10.1177/1071181322661075 article EN Proceedings of the Human Factors and Ergonomics Society Annual Meeting 2022-09-01

이 연구의 목적은 스포츠 분야 사회적기업을 둘러싸고 발생하는 여러 문제점들을 조직의 관점에서 진단하고 필요한 과제 및 시사점을 도출하는 데 있다. 목적을 달성하기 위해 크게 세 가지 단계로 구분하여 연구를 진행, 결과를 도출하 였다. 첫 번째로는 사회적기업의 주요 현황 특성 등에 대하여 살펴보았다. 배경 기원, 법제 정책, 조직목 표, 조직구조 절차, 조직특성 등의 측면을 중심으로 현황을 분석하였다. 사회적기업은 초기단계로서 정부의 사회적기업 정책목표는 재정투입을 통해 단기간 내 수를 늘리는 것에 초점을 맞추는 경향이 있었다. 그리고 개 별 기업들의 수익창출 여력이 미흡하여 보조금 지원에 의존하는 경우가 대다수인 것으로 파악되었다. 두 번째 단계에 서는 기능수행에 영향을 미치는 상황적 요인에 중점적으로 요인인 조 직의 가치와 이념, 기술, 역사 등을 검토한 결과, 사회적기업으로 인증 받아 중앙정부나 지방자치단체로부터 지 원을 받는 경우 정치적 통제는 어느 정도 강하고 시장에...

10.22678/jic.2024.22.2.073 article KO Journal of Industrial Convergence 2024-02-28
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