Interfacing between MAAP and MACCS to perform radiological consequence analysis |
Kim, Sung-yeop
(Korea Atomic Energy Research Institute)
Lee, Keo-hyoung (FNC Technology Co., Ltd.) Park, Soo-Yong (Korea Atomic Energy Research Institute) Han, Seok-Jung (Korea Atomic Energy Research Institute) Ahn, Kwang-Il (Korea Atomic Energy Research Institute) Hwang, Seok-Won (KHNP Central Research Institute) |
1 | 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. |
2 | K. McFadden, N.E. Bixler, L.L.C. Sigma Software, MelMACCS Models Document (MELCOR to MACCS Interface Description), Sandia National Laboratories, 2016. |
3 | 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. DOI |
4 | EPRI, Modular Accident Analysis Program - MAAP5 v5.04 for Windows, Electric Power Research Institute, 2016. |
5 | 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. |
6 | 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. |
7 | 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). |
8 | KAERI, Development of Site Risk Assessment & Management Technology Including Extreme External Events, Korea Atomic Energy Research Institute, 2017. KAER/RR-4225/2016. |
9 | N.E. Bixler, Brief review of ATMOS inputs, Bethesda, MD, in: MACCS Users' Workshop, 2018. June 13-15, 2018. |
10 | 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. |
11 | 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. |
12 | 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. |
13 | J.H. Seinfeld, S.N. Pandis, Atmospheric Chemistry and Physics, John Wiley & Sons, New York, 1998. |
14 | 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). |
15 | 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. |