과제정보
This research was supported by the Chung-Ang University Graduate Research Scholarship in 2018. This work was also supported by the National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIT), Republic of Korea (2017M2B2B1071973). We thank Professor Jung Ik Lee and Mr. Bong Seong Oh of Korea Advanced Institute of Science and Technology for sharing the input model for MMR used in the transient analysis.
참고문헌
- M.A. Gibson, S.R. Oleson, D.I. Poston, P. McClure, NASA's Kilopower reactor development and the path to higher power missions, in: Proceedings of the 2017 IEEE Aerospace Conference, Big Sky, MT, 2017, pp. 1-14.
- P. McClure, D. Poston, D.V. Rao, R. Reid, "Design of Megawatt Power Level Heat Pipe Reactors," LA-UR-15-28840, Los Alamos National Laboratory, 2015.
- A. Levinsky, J. van Wyk, Y. Arafat, M.C. Smith, Westinghouse eVinciTM Reactor for Off-Grid Markets, American Nuclear Society Winter Meeting, Orlando, Florida, Nov, 2018, pp. 11-15, 2018.
- C.K. Jo, Core Nuclear Design of a Micro Modular High Temperature Gas-Cooled Reactor, Transactions of the 2018 Korean Nuclear Society Autumn Meeting, Yeosu, Korea, 2018. October 25-26.
- J.S. Jun, C.K. Jo, Design Considerations of the Air-Cooled RCCS on the Very Small-Size HTGR, Transactions of the 2018 Korean Nuclear Society Autumn Meeting, Yeosu, Korea, 2018. October 25-26.
- S.G. Kim, H. Yu, J. Moon, S. Baik, Y. Kim, Y.H. Jeong, J.I. Lee, A concept design of supercritical CO2 cooled SMR operating at isolated microgrid region, Int. J. Energy Res. 41 (4) (2017) 512-525. https://doi.org/10.1002/er.3633
- B.S. Oh, Safety Analysis and Development of Control Logic of KAIST Micro Modular Reactor with GAMMA+ Code, MS Thesis, Korea Advanced Institute of Science and Technology, Department of Nuclear and Quantum Engineering, 2016.
- B.S. Oh, Y.H. Ahn, S.G. Kim, S.J. Bae, S.K. Cho, J.I. Lee, Transient analyses of S-CO2 cooled KAIST micro modular reactor with GAMMA+ code, in: Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Korean Nuclear Society, October 9-13, 2016. Gyeongju, Korea.
- H. Yu, D. Hartanto, B.S. Oh, J.I. Lee, Y. Kim, Neutronics and transient analyses of a supercritical CO2-cooled micro modular reactor (MMR), Energy Procedia 131 (2017) 21-28. https://doi.org/10.1016/j.egypro.2017.09.441
- B.S. Oh, Y.H. Ahn, H. Yu, J. Moon, S.G. Kim, S.K. Cho, Y. Kim, Y.H. Jeong, J.I. Lee, Safety evaluation of supercritical CO2 cooled micro modular reactor, Ann. Nucl. Energy 110 (2017) 1202-1216. https://doi.org/10.1016/j.anucene.2017.08.038
- KEPCO and KHNP, "Probabilistic Risk Assessment Summary Report," APR1400-E-P-NR-13001-NP, Rev. 0, Korea Electric Power, Corporation & Korea Hydro & Nuclear Power Co., Ltd, 2013.
- IAEA, "Defining Initiating Events for Purposes of Probabilistic Safety Assessment," IAEA-TECDOC-719, International Atomic Energy Agency, Vienna, September 1993.
- M.A. Pope, "Thermal Hydraulic Design of a 2400MWth Direct Supercritical CO2 Cooled Fast Reactor", Ph.D. Thesis, Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2006.
- USNRC, "Reactor Safety Study, An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants," WASH-1400, United States Nuclear Regulatory Commission, October 1975. Washington, D.C.
- H.S. Lim, "GAMMA+1.0 Vol. 2: Theory Manual," KAERI/TR-5728/2014, Korea Atomic Energy Research Institute, Daejeon, Korea, 2014.
- S.H. Han, et al., "AIMS-PSA: a software for integrated PSA. Proceedings of the 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), October 2-7, 2016. Seoul, Korea.
- IAEA, "Electric Grid Reliability and Interface with Nuclear Power Plants," IAEA Nuclear Energy Series No. NG-T-3.8, International Atomic Energy Agency, Vienna, 2012.
- R. Tregoning, L. Abramson, P. Scott, Estimating Loss-of-Coolant Accident (LOCA) Frequencies through the Elicitation Process, NUREG-1829, United States Nuclear Regulatory Commission, Washington, D.C, 2008.
- USNRC, "Rates of Initiating Events at U.S, Nuclear Power Plants: 1987-1995, NUREG/CR-5750, United States Nuclear Regulatory Commission, Washington, D.C., 1998.
- USNRC, "Industry-Averaged Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants," NUREG/CR-6928, United States Nuclear Regulatory Commission, Washington, D.C., 2007.
- W.S. Jung, S.H. Han, J. Ha, A fast BDD algorithm for large coherent fault trees analysis, Reliab. Eng. Syst. Safe. 83 (Suppl. 3) (2004) 369-374. https://doi.org/10.1016/j.ress.2003.10.009
- J. Jafaria, F. D'Auria, H. Kazeminejad, H. Davilu, Reliability evaluation of a natural circulation system, Nucl. Eng. Des. 224 (Suppl. 1) (2003) 79-104. https://doi.org/10.1016/S0029-5493(03)00105-5
- M. Marques, J.F. Pignatel, P. Saignes, F. D'Auria, L. Burgazzi, C. Muller, R. Bolado-Lavin, C. Kirchsteiger, V. La Lumia, I. Ivanov, Methodology for the reliability evaluation of a passive system and its integration into a probabilistic safety assessment, Nucl. Eng. Des. 235 (Suppl. 24) (2005) 2612-2631. https://doi.org/10.1016/j.nucengdes.2005.06.008
- A.K. Nayak, M.R. Gartia, A. Antony, G. Vinod, R.K. Sinha, Passive system reliability analysis using the APSRA methodology, Nucl. Eng. Des. 238 (Suppl. 6) (2008) 1430-1440. https://doi.org/10.1016/j.nucengdes.2007.11.005
- H.G. Lim, S.-H. Han, J.J. Jeong, Mosaique - a network based software for probabilistic uncertainty analysis of computerized simulation models, Nucl. Eng. Des. 241 (Suppl. 5) (2011) 1776-1784. https://doi.org/10.1016/j.nucengdes.2011.01.021
- J.C. Helton, F.J. Davis, Latin hypercube sampling and the propagation of uncertainty in analyses of complex systems, Reliab. Eng. System Reliab. 81 (Issue. 1) (2003) 23-69. https://doi.org/10.1016/S0951-8320(03)00058-9
- S.-J. Han, J.-E. Yang, A quantitative evaluation of reliability of passive systems within probabilistic safety assessment framework for VHTR, Ann. Nucl. Energy 37 (Suppl. 3) (2010) 345-358. https://doi.org/10.1016/j.anucene.2009.12.004
- J.S. Kim, M.C. Kim, Consistency issues in quantitative safety goals of nuclear power plants in Korea, Nuclear Eng. Technol. 51 (Suppl. 7) (2019) 1758-1764. https://doi.org/10.1016/j.net.2019.05.019