과제정보
This work was funded by the National Research Foundation of Korea (NRF) of the Ministry of Science and ICT (2020M2D7A1079182).
참고문헌
- G. Locatelli, S. Boarin, F. Pellegrino, M.E. Ricotti, Load following with small modular reactors (SMR): a real options analysis, Energy 80 (2015) 41-54. https://doi.org/10.1016/j.energy.2014.11.040
- B. Poudel, K. Joshi, R. Gokaraju, A dynamic model of small modular reactors based nuclear plant for power system studies, IEEE Trans. Eng. Conv. 35 (2020) 997, 985.
- J.H. Chun, K.-H. Lee, Y.-J. Chung, Assessment and SMART application of system analysis code, TASS/SMR-S for SBLOCA, Nucl. Eng. Des. 254 (2013) 291-299. https://doi.org/10.1016/j.nucengdes.2012.09.029
- H.-K. Kim, S.H. Kim, Y.-J. Chung, H.-S. Kim, Thermal-hydraulic analysis for SMART steam generator tube rupture using TASS/SMR-S code, Ann. Nucl. Energy 55 (2013) 331-340. https://doi.org/10.1016/j.anucene.2013.01.007
- Y.-J. Chung, B.-G. Jeon, K.-H. Bae, H.-S. Park, Validation with the MARS and TASS/SMR codes based on experimental results of a pressurizer safety valve line break at the SMART-ITL facility, Ann. Nucl. Energy 141 (2020), 107344.
- H. Bae, J.-H. Chun, E. Yun, Y.-J. Chung, S.-W. Lim, H.-S. Park, Experimental investigation and validation of TASS/SMR-S code for single-phase and two-phase natural circulation tests with SMART-ITL facility, Nucl. Eng. Technol. 54 (2022) 554-564. https://doi.org/10.1016/j.net.2021.08.023
- K.D. Kim, R. Uddin, A web-based nuclear simulator using RELAP5 and Lab-VIEW, Nucl. Eng. Des. 237 (2007) 1185-1194. https://doi.org/10.1016/j.nucengdes.2007.01.004
- C.-Y. Yang, T.K.S. Liang, B.S. Pei, C.K. Shih, S.C. Chiang, L.C. Wang, Development and application of a dual RELAP5-3D-based engineering simulator for ABWR, Nucl. Eng. Des. 239 (2009) 1847-1856. https://doi.org/10.1016/j.nucengdes.2009.05.004
- R. Schmidt, et al., An approach for coupled-code multiphysics core simulations from a common input, Ann. Nucl. Energy. 84 (2015) 140-152. https://doi.org/10.1016/j.anucene.2014.11.015
- K. Zhang, The multiscale thermal-hydraulic simulation for nuclear reactors: a classification of the coupling approaches and a review of the coupled codes, Energy Res 44 (2020) 3295-3315. https://doi.org/10.1002/er.5111
- R.K. Salko, et al., Optimization and parallelization of the thermal-hydraulic subchannel code CTF for high-fidelity multi-physics applications, Ann. Nucl. Energy. 84 (2015) 122-130. https://doi.org/10.1016/j.anucene.2014.11.005
- Y.J. Chung, I.S. Jun, S.H. Kim, S.H. Yang, H.R. Kim, W.J. Lee, Development and assessment of system analysis code, TASS/SMR for integral reactor, SMART, Nucl. Eng. Des. 244 (2012) 52-60. https://doi.org/10.1016/j.nucengdes.2011.12.013
- J. Liu, S. Yan, D. Zeng, A new measurement model for main steam flow of power plants, Proc. Environ. Sci. 11 (2011) 18-24. https://doi.org/10.1016/j.proenv.2011.12.004
- E.W. Lemmon, M.L. Huber, M.O. McLinden, NIST Standard Reference Database 23: Reference Fluid Thermodynamic and Transport Properties-REFPROP, Version 8.0, National Institute of Standards and Technology, Gaithersburg, Maryland, USA, 2007. Standard reference data program.
- KEPCO and KAERI, SMART Standard Safety Analysis Report, SSAR), 2010.