과제정보
연구 과제 주관 기관 : NRF (National Research Foundation)
참고문헌
- G. Yadigaroglu, M. Andreani, J. Dreier, and P. Coddinggton, Trends and needs in experimentation and numerical simulation for LWR safety, Nuclear Engineering and Design, 221, pp. 205-223 (2003). https://doi.org/10.1016/S0029-5493(02)00339-4
- M. Scheuerer et al., Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA), Nuclear Engineering and Design, 235, pp. 359–368 (2005). https://doi.org/10.1016/j.nucengdes.2004.08.049
- D. Bestion et al., Extension of CFD codes to two-phase flow safety problems, NEA/SEN/SIN/AMA (2006)2, OECD Nuclear Energy Agency.
- B.L. Smith et al., Assessment of CFD for nuclear reactor safety problems. Final for approval by CSNI, OECD Nuclear Energy Agency, 2007.
- U. Bieder and E. Graffard, Qualification of the CFD code Trio_U for full scale reactor applications, Nuclear Engineering and Design, 238(3), pp. 671-679 (2008). https://doi.org/10.1016/j.nucengdes.2007.02.040
- G. Yadigaroglu, Computational fluid dynamics for nuclear applications: From CFD to multi-scale CMFD, Nuclear Engineering and Design, 235(2-4), pp. 153-164 (2005). https://doi.org/10.1016/j.nucengdes.2004.08.044
- A. Guelfi et al., NEPTUNE: a new software platform for advanced nuclear thermal hydraulics, Nuclear Science and Engineering, 156(3), pp. 281-324 (2007). https://doi.org/10.13182/NSE05-98
- J.J. Jeong, H.Y. Yoon, I.K. Park, H.K. Cho, and J. Kim, A Semi-implicit numerical scheme for transient two-phase flows on unstructured grids, Nuclear Engineering and Design, 238, pp. 3403–3412 (2008). https://doi.org/10.1016/j.nucengdes.2008.08.017
- I.K. Park, H.K. Cho, H.Y. Yoon, and J.J. Jeong, Numerical effects of the semi-conservative form of momentum equations for multi-dimensional two-phase flows, Nuclear Engineering and Design, 239, pp. 2365–2371 (2009). https://doi.org/10.1016/j.nucengdes.2009.06.011
- I.K. Park, H.K. Cho, H.Y. Yoon, and J.J. Jeong, Implementations of non-drag interfacial forces into the CUPID code, Proceedings of ICAPP 2009, Tokyo, Japan, May 10-14, 2009.
- H.Y. Yoon, J.J. Jeong, I.K. Park, H.K. Cho, and H. Lee, An improved semi-implicit numerical scheme for transient three-dimensional two-phase flow analysis, The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Kanazawa, Japan, Sep. 27- Oct. 2, 2009.
- H.K. Cho, B.J. Yun, I.K. Park, and J.J. Jeong, Computational analysis of downcomer boiling phenomena using a component thermal hydraulic analysis code CUPID, to be presented at the 18th International Conference on Nuclear Engineering, Xi’an, China, May 17-21, 2010.
- The RELAP5-3D Code Development Team, RELAP5-3D code manual volume I: Code structure, system models and solution methods, Idaho National Engineering and Environmental Laboratory (2001).
- J.J. Jeong, I. Dor, and D. Bestion, Improvement and assessment of the CATHARE2 three-dimensional module compared with the UPTF downcomer test 7, Nuclear Technology, 117, pp. 267-280 (1997).
- B.J. Yun, D.J. Euh, and C.H. Song, Investigation of the downcomer boiling phenomena during the reflood phase of a postulated large-break LOCA in the APR1400, Nuclear Technology, 156, pp. 56-68 (2006).
- J.J. Jeong, K.S. Ha, B.D. Chung, and W.J. Lee, Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1, Annals of Nuclear Energy, 26(18), pp. 1611- 1642 (1999). https://doi.org/10.1016/S0306-4549(99)00039-0
- C. Frepoli, J.H. Mahaffy, and K. Ohkawa, Notes on the implementation of a fully-implicit numerical scheme for a two-phase three-field flow model, Nuclear Engineering and Design, 225, pp. 191-217 (2003). https://doi.org/10.1016/S0029-5493(03)00159-6
- D.R. Liles and W.H. Reed, A semi-implicit method for twophase fluid dynamics, J. Comput. Phys., 26, pp. 390-407 (1978). https://doi.org/10.1016/0021-9991(78)90077-3
- H.Y. Yoon et al., An unstructured SMAC algorithm for thermal non-equilibrium two-phase flows, Int. Communications in Heat and Mass Transfer, 36, pp. 16–24 (2009). https://doi.org/10.1016/j.icheatmasstransfer.2008.08.015
- C.M. Rhie, and W.L. Chow, Numerical study of the turbulent flow past an airfoil with trailing edge separation, AIAA Journal 21(11), pp. 1525-1532 (1983). https://doi.org/10.2514/3.8284
- N.T. Frink, Recent progress toward a three-dimensional unstructured Navier-Stokes flow solver, AIAA Paper 94- 0061 (1994).
- T.J. Barth and D.C. Jesperson, The design and application of upwind schemes on unstructured meshes, AIAA Paper 89-0366 (1989).
- V. Venkatakrishnan, Convergence to steady state solutions of the Euler equations on unstructured grids with limiters, Journal of Computational Physics, 118, pp. 120–130 (1995). https://doi.org/10.1006/jcph.1995.1084
- H.D. Lee, A new method for the reconstruction of the pressure gradient for the CUPID code, CTHA-2009-005, Korea Atomic Energy Research Institute (2009).
- W.L. Oberkampf and T.G. Trucano "Verification and validation benchmarks," Nuclear Engineering and Design, 238, 716–743 (2008). https://doi.org/10.1016/j.nucengdes.2007.02.032
- H. Staedtke, Gas dynamic aspects of two-phase flow, Wiley- VCH Verlag GmbH & Co. KGaA Weinheim, pp. 143-147 (2006).
- FLUENT 6.3 user’s guide, Fluent Inc. (2006).
- T. Nagatake, Z. Kawara, and T. Kunugi, Establishment of experimental data base on dam-breaking problem for validating interface tracking methods, NTHAS6: Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, Okinawa, Japan, Nov. 24-27, 2008.
- D.J. Euh et al., Experimental characterization of co-current subcooled boiling phenomena in a rectangular geometry, to be presented at HEFAT2010, 7th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, 19-21 July, Antalya, Turkey, 2010.
- J.W. Spore et al., TRAC-M/FORTRAN 90 (VERSION 3.0) THEORY MANUAL, LA-UR-00-910, Los Alamos National Laboratory, 2000.
- M. Ishii, Personal communication to R. Nelson, Los Alamos National Laboratory, 1987.
피인용 문헌
- Computational Analysis of Downcomer Boiling Phenomena Using a Component Thermal Hydraulic Analysis Code, CUPID vol.133, pp.5, 2011, https://doi.org/10.1115/1.4002869
- THE DEVELOPMENT AND ASSESSMENT STRATEGY OF A THERMAL HYDRAULICS COMPONENT ANALYSIS CODE vol.16, pp.2, 2011, https://doi.org/10.6112/kscfe.2011.16.2.030
- Preliminary Analysis of the CANDU Moderator Thermal-Hydraulics using the CUPID Code vol.21, pp.4, 2012, https://doi.org/10.5855/ENERGY.2012.21.4.419
- Assessment of the two-phase flow models in the CUPID code using the downcomer boiling experiment vol.49, pp.1, 2012, https://doi.org/10.1080/18811248.2011.636560
- VERIFICATION OF TURBULENCE AND NON-DRAG INTERFACIAL FORCE MODELS OF A COMPUTATIONAL MULTI-FLUID DYNAMICS CODE vol.18, pp.2, 2013, https://doi.org/10.6112/kscfe.2013.18.2.099
- Preliminary Thermal-Hydraulic Analysis of the CANDU Reactor Moderator Tank using the CUPID Code vol.23, pp.4, 2014, https://doi.org/10.5855/ENERGY.2014.23.4.095
- NATURAL CIRCULATION ANALYSIS CONSIDERING VARIABLE FLUID PROPERTIES WITH THE CUPID CODE vol.20, pp.4, 2015, https://doi.org/10.6112/kscfe.2015.20.4.014
- Experiment on water turbulent natural convection for safety improvement of nuclear power plant vol.14, pp.3, 2016, https://doi.org/10.5407/JKSV.2016.14.3.046