MURRG, 다수기 PSA 규제검증 기술개발 사업단

Hanyang University

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Research Content

  • Research Scope

    Nuclear Safety Analysis Laboratory performs the task to develop the methodology of Site Risk Assessment(SRA) and the Site Risk Assessment Model with AIMS, FTREX, MACCS code.

    Single-unit PRA models for OPR1000, APR1400, WH600 and WH900 would be developed and expanded to develop SRA model for all units in operation at the site. A result of research would be used as verification of result of SRA and a technical resource for a development of the site risk regulatory methodology

    As a task of chief, a management and operation of MURRG’s tasks as well as a self-evaluation of research result of each sub-project would be conducted.

  • Expected Effect

    It will establish the basis of SRA and contribute to the prevention and mitigation of accidents in densely populated reactors and to the enhancement of safety by drawing out multi-unit accident scenarios and establishing countermeasures.

    It will provides a technical basis of establishing regulatory standards/guidelines for independent verification and review of SRA results.

Figure 1. Research steps and content

Classficaton Computational Codes
Level 1 & 2 PSA AIMS-PSA/FTREX 1.2c, SAREX
Severe Accident Simulation MELCOR 2.2, MAAP4, MARS

Table 1. Computational Codes for the development of SRA model

Research Results

  • Development of Single-Unit full power PRA models for OPR1000, APR1400, WH600 and WH900

    Development of Single-unit full power PRA models giving consideration to multi-unit accident

    Development of MELCOR input model for Source Term Category(STC) evaluation

Figure 2. RCS and Reactor Building of MELCOR Nodalization of Reference Plant

  • Assessment of Single-Unit Risk

    Assessment of single-unit containing multi-unit accident

  • Figure 3. Risk Profile of 4 Units in MU-LOOP Accident

  • Figure 4. Risk Profile of 1 Unit in MU-LOOP Accident

  • Figure 5. Risk Profile of 2 Units in MU-LOOP Accident

  • Figure 6. Risk Profile of 3 Units in MU-LOOP Accident

  • Development of PRA model and Analysis of Current Issues

    Assessment of Containment Integrity giving consideration into Mobile Diesel Generator(MDG) and Containment Filtered Venting System(CFVS)

  • Development of Multi-Unit Risk Assessment

    Offsite power recovery modeling

    Inter-unit CCF modeling

    Development and application of multi-unit STC analysis methodology

Figure 7. Example of Multi-unit Level 1 PRA Top Logic

  • Assessment of Multi-Unit Risk

    Development and Assessment of Multi-unit risk model based on single-unit model

    Accident management of site containing multi-unit and multi-unit risk monitoring

Researcher profile

  • E-mail
  • Tel. +82-2-2220-4951
  • Fax. +82-2-2220-4954

Prof. Moosung Jae

  • Academic Background

    UCLA Nuclear Engineering, Ph. D. (USA)

    Seoul Univ. Nuclear Engineering Master

    Seoul Univ. Nuclear Engineering Bachelor

  • Career

    Hanyang University, Professor

    IAEA International Nuclear Safety Group(INSAG), Member

    Nuclear Safety and Security Commission-Nuclear Safety Safety special Committee, Chair

    Korean Nuclear Society-Nuclear Safety Division, Chair

    Multi-Unit Risk Research Group ,Director

    The National Academy of Engineering of Korea, member

  • Researchers
    No. Name Position No. Name Position
    1 Youngho Jin Executive Director 10 Yein Seo Master’s Course
    2 Dongha Kim Research Professor 11 Hyunae Park Master’s Course
    3 Joohyun Park Administrative office manager 12 Byeongmun Ahn Master’s Course
    4 Seunghyun Jang Ph.D. Course 13 Sangyeon Kim Master’s Course
    5 Sunghyun Park Ph.D. Course 14 Yerim Park Master’s Course
    6 Hoyoung Shin Ph.D. Course 15 Mina Cho Master’s Course
    7 Dohyun Lim Ph.D. Course 16 Seokwoo Sohn Master’s Course
    8 Seungwoo Kim Ph.D. Course 17 Youngjin Kim Master’s Course
    9 Wonjong Song Master’s Course 18