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원자력안전해석연구실NASA Lab

Nuclear Safety Analysis Laboratory

NASA Lab
제무성교수
교수정보
전화 02-2220-1790
이메일 jae@hanyang.ac.kr
위치 국제관 406호
홈페이지 https://nasalab.hanyang.ac.kr/
연구분야 · Probabilistic Risk Assessments
· 중대사고 분석
· 계통신뢰도 분석
· 위험도정보 규제기술

1. 연구실 소개

보유장비
AIMS, SAREX, RISKMAN (1단계 PRA)
MELCOR, MAAP, CONPAS (2단계 PRA)
MACCS2, WinMACCS, RASCAL (3단계 PRA)
MUDAP, CORSIM, MSPAR, VENSIM (기타)
연구실 특징
원전 안전해석 및 중대사고 리스크 평가
발전소 사고 분석과 예방 및 사고완화를 위하여 필요한 안전 계통 분석과 운전원 신뢰도분석, 사고시나리오별 주요 시스템의 성공기준 분석 등 체계적 안전 분석을 통하여 발생가능한 노심손상 사고경위와 그 발생빈도를 정량적으로 평가
노심손상 이후 격납건물 내의 중대사고 현상 및 방사성 물질 이동을 체계적으로 분석하고 격납건물 파손 형태, 파손 가능성, 격납건물 외부로 방출되는 노심 핵종별 방사성 물질의 양과 방출 가능성을 정량적으로 평가
원전 중대사고 시 소외로 방출되는 방사성 물질로 인해 야기되는 대중에 대한 위험도를 정량적으로 평가하고 기상조건과 지형에 따른 방사선 물질의 대기 중 확산 및 침적, 흡입 등을 고려하여 인체 및 소외 환경에 미치는 피해를 정량적으로 평가

  연구 분야별 최근 주요 연구논문 및 보고서

 

1. 최근 주요 연구논문

 

- Hyunae Park, Moosung Jae, "Uncertainty analysis of source term and off-site consequence for WH600 using MELCOR and WinMACCS", Annals of Nuclear Energy 175, 109175, 2022.

- Seoungwoo Kim, Yerim Park, Youngho Jin, Dong Ha Kim, Moosung Jae, "Effect analysis of ISLOCA pathways on fission product release at Westinghouse 2-loop PWR using MELCOR", Nuclear Engineering and Technology 53, 2878e2887, 2021.

- Junghyun Ryu, Moosung Jae, "A quantification methodology of Seismic Probabilistic Safety Assessment for nuclear power plant", Annals of Nuclear Energy 159, 108296, 2021.

- Sunghyun Park, Moosung Jae, "A Staged Evacuation Methodology for Emergency Preparedness Plan", Journal of Nuclear Science and Technology, https://doi.org/10.1080/00223131.2021.1934584, 2021.

- Sunghyun Park, Seokwoo Sohn, Moosung Jae, "Cohort-based evacuation time estimation using TSIS-CORSIM", Nuclear Engineering and Technology 53, 1979e1990, 2021.

- Yerim Park, Hoyoung Shin, Seungwoo Kim, Youngho Jin, Dong Ha Kim, Moosung Jae, "Analysis of severe accident progression and Cs behavior for SBO event during mid-loop operation of OPR1000 using MELCOR", Nuclear Engineering and Technology 53, 2859e2865, 2021.

- Yein Seo, Seunghyun Jang, Sunghyun Park, Moosung Jae, "A preliminary site risk assessment", Journal of Nuclear Science and Technology, 58:7, 822-836, 2021

- Hoyoung Shin, Moosung Jae, "Realistic evaluation of source terms for steam generator tube rupture accidents", Annals of Nuclear Energy 164, 108559, 2021.

- Hoyoung Shin, Seungwoo Kim, Yerim Park, Youngho Jin, Dong Ha Kim, Moosung Jae, "Analysis of fission product reduction strategy in SGTR accident using CFVS", Nuclear Engineering and Technology 53, 812e824, 2021.

- Seunghyun Jang , Yongjin Kim , Moosung Jae, "A site risk assessment for internal events: A case study ", Reliability Engineering and System Safety 215, 107876, 2021.

- Junghyun Ryu, Moosung Jae, "Equipment Selection Methodology of Seismic Probability Safety Assessment for Nuclear Power Plant", atw Vol. 66, Issue 6, 2021.

- Wonjong Song, Sunghyun Park, Yein Seo, Moosung Jae, "A source term binning methodology for multi-unit consequence analyses", Reliability Engineering and System Safety 202, 106989, 2020.

- Sunghyun Park, Seokwoo Sohn, Moosung Jae, "Cohort-based evacuation time estimation using TSIS-CORSIM", Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2020.11.028, 2020.

- Hoyoung Shin, Seungwoo Kim, Yerim Park, Youngho Jin, Dong Ha Kim, Moosung Jae, "Analysis of fission product reduction strategy in SGTR accident using CFVS", Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2020.08.003, 2020.

- Seunghyun Jang, Moosung Jae, "A development of methodology for assessing the inter-unit common cause failure in multi-unit PSA model", Reliability Engineering and System Safety 203, 107012, 2020.

- Wonjong Song, Hoyoung Shin, Myeonghyeon Woo, Min Baek, Moosung Jae, "An uncertainty Analysis for a Head End Process in the Pyroprocessing", atw Vol.64, Issue 10, 2019.

- Dahye Kwon, Won-Tae Hwang, Moosung Jae, "Ingestion Dose Evaluation of Korean Based on Dynamic Model in a Severe Accident", Journal of Radiation Protection and Research 43(2), 50-58, 2018.

- Jintae Kim, Moosung Jae, "A study on reliability assessment of a decay heat removal system for a sodium-cooled fast reactor", Annals of Nuclear Energy Volume 120, Pages 534-539, 2018.

- Gunhyo Jung, Moosung Jae, "Quantitative assessment of severe accident management strategies in a nuclear power plant", JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 2018, https://doi.org/10.1080/00223131.2018.1428123, 2018.

- Seunghyun Jang, Sunghyun Park, and Moosung Jae, "Development of an Accident Sequence Precursor Methodology and its Application to Significant Accident Precursors", Nuclear Engineering and Technology Volume 49, Issue 2, Pages 313-326, 2017.

- Joeun Lee, Jintae Kim and Moosung Jae, "A Probabilistic Consequence Assessment for a Very High Temperature Reactor", atw Vol. 62, Issue 2, 2017.

- Kiyoon Han and Moosung Jae, "Development of a New Methodology for Quantifying Nuclear Safety Culture", atw Vol. 62, Issue 1, 2017.

 

2. 최근 주요 보고서

 

- "Development of a methodology of AAC DG sharing model in Multi-unit PSA", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-21NS22-138.

- "Development of a methodology of Multi-unit off-site power recovery modeling in Multi-unit PSA", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-21NS22-139.

- "Development of the Site Safety Index(SSI) for a Reference Site Considering Multi-Unit Risk Effects", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-21NS23-137.

- "Consequence and release frequency assessment for source term categories on a reference site", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-21NS22-136.

- "Development and Application of Level 1, 2 and 3 PSA Methodology for Twin Nuclear Power Plants", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-21NS22-135.

- "Study on How to Regulate the Risk of the Individual Nuclear Power Plant Considering Multi-unit Effect", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-23NS11-193.

- "A Comparative Study on the Utilization Strategies of Mobile Equipment against Extreme Hazards in Nuclear Power Plants at Home and Abroad", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021. NSTAR-21NS11-47.

- "Assessment of External Water Injection Effects of the Portable Pumps using Decision Tree Methodology", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-21NS11-47.

- "Analysis of the Effect of the External Injection into the RCS and SG Using Portable Equipment on the Containment Performance During Severe Accident", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2021, NSTAR-21NS12-48.

- "Development of a Database Management Program for Multi-unit PSA", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2020, NSTAR-20NS22-98.

- "A Study on Uncertainty Analysis Methodology for Source Term of Nuclear Power Plant", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2020, NSTAR-20NS12-37.

- "Preliminary Uncertainty Analysis for Level 3 PSA using WinMACCS", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2020, NSTAR-20NS12-36.

- "Development of a Source-term Grouping Methodology for Multi-unit Level 3 PSA", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2020, NSTAR-20NS22-35.

- "Development of Source Term Categories Grouping Methodology Base on Dose-Estimates for Site Risk Assessment of Nuclear Power Plants", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2020, NSTAR-20NS22-100.

- "Development of Level 2 PSA Code, COFUN", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2020, NSTAR-20NS22-34.

- "The Korean industry-average initiating event analysis for site risk assessment", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2020,NSTAR-20NS22-99.

- "Rascal Off-Site Consequence Assessment Method Analysis", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19RS42-80.

- "A Study of Seismic Correlation Analysis Methodology for Multi-unit Seismic PSA", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19NS22-89.

- "Analysis of Sever Accident Thermal-Hydraulic Phenomena for a Small Loss of Coolant Accident at Kori and Saeul Sites Using MELCOR", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19NS22-75.

- "An Evaluation of Core Inventory for Reactor Types by using ORIGEN", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19NS12-82.

- "Consequence Analysis using HYSPLIT Code", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19NS12-81.

- "Development of Korean Food Chain Model for Level 3 PSA", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19NS22-38.

- "Development of Methodology for Multi-unit Level 1, 2 PSA", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19NS22-33.

- "Evacuation Time Estimates on The Reference Nuclear Power Plant", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019, NSTAR-19RS42-62.

- "An Analysis of Economic Factors in a Domestic Environment for Probabilistic Safety Assessment", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2019. NSTAR-19NS22-39.

- "Development of Single-unit Level 2 Full Power Internal Event PSA Model for Regulation Verification", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2018, NSTAR-18NS12-23.

- "A Study on MACCS Input Parameters for a Level 3 PSA Model For Regulation Verification", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2018, NSTAR-18NS12-24.

 

 

- "A Sensitivity Analysis on the Level 3 PSA Model for Regulation Verification", Nuclear Safety and Security Commision & Korea Foundation of Nuclear Safety, 2018, NSTAR-18NS12-25.

2. 주요 연구 / 프로젝트

원전 중대사고 리스크 분석(PRA)
원전 신뢰도 분석(Level 1 PRA 분석용 코드: AIMS, SAREX, RISKMAN 등)
원전 중대사고 분석(Level 2 PRA 분석용 코드: MELCOR, MAAP, CONPAS 등)
원전 사고 피해 분석(Level 3 PRA 분석용 코드: MACCS2, WinMACCS, RASCAL 등)

규제검증용 Level 2 PSA 모델 개발

 중대사고 코드(MELCOR)를 이용한 방사선원항 분석

 격납건물 건전성 평가(LERF 등 격납건물 파손확률 분석)

 Level 1 및 Level 2를 포함하는 불확실성 분석코드, COFUN 개발

 최신기술 기준을 반영한 PDSLD, CET, DET, STC 구성

 

규제검증용 다수기 리스크 평가기술 개발
다수기 중대사고 빈도 및 피해 평가방법 개발
다수기 사고피해 분석방법 개발
부지 리스크 평가 및 리스크 프로파일 기술개발
정지저출력 SRA 규제방법론 개발

·소듐냉각고속로, 고온가스로 등 SMR(Small Modular Reactors) 원전 리스크 분석

- 소듐냉각고속로, 고온가스로 등 SMR 원전 설계특성 분석

- 불확실성을 고려한 소듐냉각고속로 등 피동안전계통 신뢰도 평가방법론 개발

- 개발된 평가방법론의 SMR 원전 피동계통에 적용

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