Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Interfacing between MAAP and MACCS to perform radiological consequence analysis

  • Received : 2021.05.19
  • Accepted : 2021.10.02
  • Published : 2022.04.25
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Abstract

Interfacing the output of severe accident analysis with the input of radiological consequence analysis is an important and mandatory procedure at the beginning of Level 3 PSA. Such interfacing between the severe accident analysis code MELCOR and MACCS, one of the most commonly used consequence analysis codes, is relatively tractable since they share the same chemical groups, and the related interfacing software, MelMACCS, has already been developed. However, the linking between MAAP, another frequently used code for severe accident analyses, and MACCS has difficulties because MAAP employs a different chemical grouping method than MACCS historically did. More specifically, MAAP groups by chemical compound, while MACCS groups by chemical element. An appropriate interfacing method between MAAP and MACCS has therefore long been requested by users. This study suggests a way of extracting relevant information from MAAP results and providing proper source term information to MACCS by an appropriate treatment. Various parameters are covered in terms of magnitude and manner of release in this study, and special treatment is made for a bypass scenario. It is expected that the suggested approach will provide an important contribution as a guide to interface MAAP and MACCS when performing radiological consequence analyses.

Keywords

Acknowledgement

This work was supported by a National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIT: Ministry of Science, ICT) (No. 2017M2A8A4015289). In addition, this work was carried out partially supported by the 'Development of the Level 2&3 PSA Technologies based on the State-of-the-Art Technology (L16S059000)' project, funded by the Central Research Institute (CRI) of Korea Hydro and Nuclear Power (KHNP) Co., Ltd.

References

  1. N. Bixler, F. Walton, J. Leute, L. Eubanks, R. Haaker, K. McFadden, MACCS (MELCOR Accident Consequence Code System) User Guide, Sandia National Laboratories, 2021. SAND2021-1588.
  2. U.S. NRC, Severe accident risks: an assessment for five U.S. Nuclear power plants, U.S. Nuclear regulatory commission. NUREG-1150 Appendix B, 1990.
  3. N.E. Bixler, J. Jones, D. Osborn, S. Weber, J. Barr, MACCS best practices as applied in the state-of-the-art reactor consequence analyses (SOARCA) project, U.S. Nuclear regulatory commission, 2014. NUREG/CR-7009.
  4. U.S. NRC, Reactor Safety Study: an Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, U.S. Nuclear Regulatory Commission, 1975. NUREG-75/014 (WASH-1400).
  5. FAI, MAAP4 Modular Accident Analysis Program for LWR Power Plants User's Manual, Fauske & Associates LLC, May 1994-June 2005. Project RP3131-02 (prepared for EPRI).
  6. EPRI, Modular Accident Analysis Program - MAAP5 v5.04 for Windows, Electric Power Research Institute, 2016.
  7. KAERI, Development of Site Risk Assessment & Management Technology Including Extreme External Events, Korea Atomic Energy Research Institute, 2017. KAER/RR-4225/2016.
  8. ASME/ANS, Standard for Radiological Accident Offsite Consequence Analysis (Level 3 PRA) to Support Nuclear Installation Applications, American Nuclear Society, 2017. ASME/ANS RA-S-1.3-2017.
  9. K. McFadden, N.E. Bixler, L.L.C. Sigma Software, MelMACCS Models Document (MELCOR to MACCS Interface Description), Sandia National Laboratories, 2016.
  10. J.H. Seinfeld, S.N. Pandis, Atmospheric Chemistry and Physics, John Wiley & Sons, New York, 1998.
  11. SNL, U.S. NRC, State-of-the-Art Reactor Consequence Analyses (SOARCA) Project: Sequoyah Integrated Deterministic and Uncertainty Analyses, U.S. Nuclear Regulatory Commission, 2019. NUREG/CR-7245.
  12. N.E. Bixler, Brief review of ATMOS inputs, Bethesda, MD, in: MACCS Users' Workshop, 2018. June 13-15, 2018.
  13. L.L. Humphries, B.A. Beeny, F. Gelbard, D.L. Louie, J. Phillips, H. Esmaili, MELCOR Computer Code Manuals, in: Reference Manual, Version 2.2.9541 2017, 2, U.S. Nuclear Regulatory Commission, Washington, 2017. SAND2017-0876 O.
  14. N.E. Bixler, E. Clauss, C.W. Morrow, J.A. Mitchell, C. Navarro, J. Barr, Synthesis of Distributions Representing Important Non-site-specific Parameters in Off-Site Consequence Analyses, U.S. Nuclear Regulatory Commission, 2014. NUREG/CR-7161.
  15. S.Y. Kim, N.E. Bixler, K.I. Ahn, S.W. Hwang, An approach to incorporate multiple forms of iodine in radiological consequence analysis, J. Environ. Radioact. 213 (2020) 106139, https://doi.org/10.1016/j.jenvrad.2019.106139.