참고문헌
- D. Delmastro, An advanced integrated PWR, in: International Seminar Held in Cairo, Egypt, 2002, pp. 27-31.
- International Atomic Energy Agency (IAEA), Status of Small and Medium Sized Reactor Designs, 2012, pp. 4-5. https://aris.iaea.org/Publications/smr-statussep-2012.pdf.
- C.P. Marcel, F.M. Acuna, P.G. Zanocco, D.F. Delmastro, Stability of selfpressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: the stability performance of the CAREM-25 reactor, Nucl. Eng. Des. 265 (2013) 232-243. https://doi.org/10.1016/j.nucengdes.2013.08.057
- C.P. Marcel, H.F. Furci, D.F. Delmastro, V.P. Masson, Phenomenology involved in self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: the thermalehydraulics of the CAREM-25 reactor, Nucl. Eng. Des. 254 (2013) 218-227. https://doi.org/10.1016/j.nucengdes.2012.09.005
- P. Zanocco, D. Delmastro, M. Gimenez, Linear and nonlinear stability analysis of a self-pressurized, natural circulation, integral reactor, in: ICONE12, International Conference on Nuclear Engineering, 2004. Washington, DC.
- P. Zanocco, M. Gimenez, D. Delmastro, Modeling aspects in linear stability analysis of a self-pressurized natural circulation integral reactor, Nucl. Eng. Des. 231 (2004) 283-301. https://doi.org/10.1016/j.nucengdes.2004.03.006
- S.E. Arda, K.E. Holbert, Nonlinear dynamic modeling and simulation of a passively cooled small modular reactor, Prog. Nucl. Energy 91 (2016) 116-131. https://doi.org/10.1016/j.pnucene.2016.03.033
- S.E. Arda, K.E. Holbert, A dynamic model of a passively cooled small modular reactor for controller design purposes, Nucl. Eng. Des. 289 (2015) 218-230. https://doi.org/10.1016/j.nucengdes.2015.04.026
- Inc, RELAP5/MOD3.3 Code Manual, Volume II, Appendix A, Input Requirements, 2002.
- International Atomic Energy Agency (IAEA), Status of Innovative Small and Medium Sized Reactor Designs, 2006. http://pub.iaea.org/MTCD/publications/PDF/te-1485-web.pdf.
- D.L. Hetrick, Dynamics of Nuclear Reactor, The University of Chicago Press, 1971.
- R.E. Skinner, E.R. Cohen, Reduced delayed neutron group representation, Nucl. Sci. Eng. (1959) 5-291.
- G.R. Ansarifar, Control of the nuclear steam generators using adaptive dynamic sliding mode method based on the nonlinear model, Ann. Nucl. Energy 88 (2016) 280-300. https://doi.org/10.1016/j.anucene.2015.11.014
- F.P. Incropera, Fundamentals of Heat and Mass Transfer, John Wiley & Sons, 2011.
- L. Zhao, L. Guo, B. Bai, Y. Hou, X. Zhang, Convective boiling heat transfer and two-phase flow characteristics inside a small horizontal helically coiled tubing once-through steam generator, Int. J. Heat Mass Transf 46 (25) (2003) 4779-4788. https://doi.org/10.1016/S0017-9310(03)00354-5
- Electric Power Research Institute (EPRI), Pressurized Water Reactor Modeling for Long-term Power System Dynamics Simulation, 1983.
- R.E. Sonntag, C. Borgnakke, G.J. Van Wylen, Fundamental of Thermodynamic, John Wiley & Sons Press, 2003.
- Mathworks, SIMULINK Dynamic System Simulation Language User's Guide, 2016.
- Z.L. Wang, W.X. Tian, G.H. Su, S.Z. Qiu, L. Zhao, Q.L. Zuo, Y.W. Wu, D.L. Zhang, Development of a thermal hydraulic code for an integral reactor, Prog. Nucl. Energy 68 (2013) 31-42. https://doi.org/10.1016/j.pnucene.2013.04.010
피인용 문헌
- Developing a robust and flexible smart tool to predict a full range Critical Heat Flux (CHF) in different LWRs by using deep learning Artificial Neural Networks (ANN) via parallel multi-processing vol.142, pp.None, 2018, https://doi.org/10.1016/j.pnucene.2021.103985