Nuclear Engineering and Technology

  • 제50권5호
  • /
  • Pages.654-664
  • /
  • 2018
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Self-pressurization analysis of the natural circulation integral nuclear reactor using a new dynamic model

  • Pilehvar, Ali Farsoon (Department of Nuclear Engineering, Faculty of Advanced Sciences & Technologies, University of Isfahan) ;
  • Esteki, Mohammad Hossein (Department of Biomedical Engineering, Faculty of Engineering & Technologies, University of Isfahan) ;
  • Hedayat, Afshin (Reactor and Nuclear Safety School, Nuclear Science and Technology Research Institute (NSTRI)) ;
  • Ansarifar, Gholam Reza (Department of Nuclear Engineering, Faculty of Advanced Sciences & Technologies, University of Isfahan)
  • 투고 : 2017.09.13
  • 심사 : 2018.03.13
  • 발행 : 2018.06.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

Self-pressurization analysis of the natural circulation integral nuclear reactor through a new dynamic model is studied. Unlike conventional pressurized water reactors, this reactor type controls the system pressure using saturated coolant water in the steam dome at the top of the pressure vessel. Self-pressurization model is developed based on conservation of mass, volume, and energy by predicting the condensation that occurs in the steam dome and the flashing inside the chimney using the partial differential equation. A simple but functional model is adopted for the steam generator. The obtained results indicate that the variable measurement is consistent with design data and that this new model is able to predict the dynamics of the reactor in different situations. It is revealed that flashing and condensation power are in direct relation with the stability of the system pressure, without which pressure convergence cannot be established.

키워드

참고문헌

  1. D. Delmastro, An advanced integrated PWR, in: International Seminar Held in Cairo, Egypt, 2002, pp. 27-31.
  2. 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.
  3. 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
  4. 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
  5. 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.
  6. 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
  7. 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
  8. 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
  9. Inc, RELAP5/MOD3.3 Code Manual, Volume II, Appendix A, Input Requirements, 2002.
  10. 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.
  11. D.L. Hetrick, Dynamics of Nuclear Reactor, The University of Chicago Press, 1971.
  12. R.E. Skinner, E.R. Cohen, Reduced delayed neutron group representation, Nucl. Sci. Eng. (1959) 5-291.
  13. 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
  14. F.P. Incropera, Fundamentals of Heat and Mass Transfer, John Wiley & Sons, 2011.
  15. 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
  16. Electric Power Research Institute (EPRI), Pressurized Water Reactor Modeling for Long-term Power System Dynamics Simulation, 1983.
  17. R.E. Sonntag, C. Borgnakke, G.J. Van Wylen, Fundamental of Thermodynamic, John Wiley & Sons Press, 2003.
  18. Mathworks, SIMULINK Dynamic System Simulation Language User's Guide, 2016.
  19. 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

  1. 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