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For the analysis of transient two-phase flows in nuclear reactor components, a three-dimensional thermal hydraulics code, named CUPID, has been developed. The CUPID code adopts a two-fluid, three-field model for two-phase flows, and the governing equations were solved over unstructured grids, which are very useful for the analysis of flows in complicated geometries. To obtain numerical solutions, the semi-implicit numerical method for the REALP5 code was modified for an application to unstructured grids, and it has been further improved for enhanced accuracy and fast running. For the verification of the CUPID code, a set of conceptual problems and experiments were simulated. This paper presents the flow model, the numerical solution method, and the results of the preliminary assessment.

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기사명 저자명 페이지 원문 목차
Managing spent nuclear fuel from non-proliferation, security and environmental perspectives Jor-Shan Choi pp.231-236

Review and future issues on spent nuclear fuel storage T. Saegusa, K. Shirai, T. Arai, J. Tani, H. Takeda, M. Wataru, A. Sasahara, P.L. Winston pp.237-248

The effects of creep and hydride on spent fuel integrity during interim dry storage Hyun-Gil Kim, Yong-Hwan Jeong, Kyu-Tae Kim pp.249-258

Development and validation of coupled dynamics code 'TRIKIN' for VVER reactors Obaidurrahman K., J.B. Doshi, R.P. Jain, V. Jagannathan pp.259-270

Monte Carlo depletion under leakage-corrected critical spectrum via albedo search Sunghwan Yun, Nam Zin Cho pp.271-278

Development and preliminary assessment of a three-dimensional thermal hydraulics code, CUPID Jae Jun Jeong, Han Young Yoon, Ik Kyu Park, Hyoung Kyu Cho, Heedong Lee pp.279-296

Enhancement of dryout heat flux in a debris bed by forced coolant flow from below Kwang-Hyun Bang, Jong-Myung Kim pp.297-304

Protection sequence of AC/DC converters for ITER PF magnet coils Byung-Hoon Oh, Churl-Kew Hwang, Kwang-Won Lee, Jeong-Tae Jin, Dae-Sik Chang, Jong-Seok Oh, Jungwan Choi, Jae Hak Suh, Jun Tao, Inho Song pp.305-312

Application of alanine/ESR spectrum shape change in gamma dosimetry Hoon Choi, Jeong In Kim, Byung Ill Lee, Young Ki Lim pp.313-318

A sensitivity analysis of the key parameters for the prediction of the prestress force on bonded tendons Jung Bum Jang, Hong Pyo Lee, Kyeong Min Hwang, Young Chul Song pp.319-338

DEVELOPMENT OF REACTOR POWER CONTROL LOGIC FOR THE POWER MANEUVERING OF KALIMER-600 SEUNG-HWAN SEONG, HAN-OK KANG, SEONG-O KIM pp.329-338

참고문헌 (31건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 Trends and needs in experimentation and numerical simulation for LWR safety 네이버 미소장
2 Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA) 네이버 미소장
3 3 ] D. Bestion et al., Extension of CFD codes to two-phase flow safety problems, NEA/SEN/SIN/AMA (2006)2, OECD Nuclear Energy Agency. 미소장
4 4 ] B.L. Smith et al., Assessment of CFD for nuclear reactor safety problems. Final for approval by CSNI, OECD Nuclear Energy Agency, 2007. 미소장
5 Qualification of the CFD code Trio_U for full scale reactor applications 네이버 미소장
6 Computational Fluid Dynamics for nuclear applications: from CFD to multi-scale CMFD 네이버 미소장
7 NEPTUNE: A New Software Platform for Advanced Nuclear Thermal Hydraulics 네이버 미소장
8 A semi-implicit numerical scheme for transient two-phase flows on unstructured grids 네이버 미소장
9 Numerical effects of the semi-conservative form of momentum equations for multi-dimensional two-phase flows 네이버 미소장
10 10 ] 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. 미소장
11 11 ] 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. 미소장
12 12 ] 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. 미소장
13 13 ] 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). 미소장
14 Improvement and Assessment of the CATHARE 2 Three-Dimensional Module Compared with the UPTF Downcomer Test 7 네이버 미소장
15 Investigation of the Downcorner Boiling Phenomena During the Reflood Phase of a Postulated Large-Break LOCA in the APR1400 네이버 미소장
16 Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1 네이버 미소장
17 Notes on the implementation of a fully-implicit numerical scheme for a two-phase three-field flow model 네이버 미소장
18 A semi-implicit method for two-phase fluid dynamics 네이버 미소장
19 19 ] 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). 미소장
20 Numerical study of the turbulent flow past an airfoil with trailing edge separation 네이버 미소장
21 21 ] N.T. Frink, Recent progress toward a three-dimensional unstructured Navier-Stokes flow solver, AIAA Paper 94- 0061 (1994). 미소장
22 22 ] T.J. Barth and D.C. Jesperson, The design and application of upwind schemes on unstructured meshes, AIAA Paper 89-0366 (1989). 미소장
23 Convergence to Steady State Solutions of the Euler Equations on Unstructured Grids with Limiters 네이버 미소장
24 24 ] 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). 미소장
25 Verification and validation benchmarks 네이버 미소장
26 26 ] H. Staedtke, Gas dynamic aspects of two-phase flow, Wiley- VCH Verlag GmbH & Co. KGaA Weinheim, pp. 143-147 (2006). 미소장
27 27 ] FLUENT 6.3 user’s guide, Fluent Inc. (2006). 미소장
28 28 ] 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. 미소장
29 29 ] 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. 미소장
30 30 ] J.W. Spore et al., TRAC-M/FORTRAN 90 (VERSION 3.0) THEORY MANUAL, LA-UR-00-910, Los Alamos National Laboratory, 2000. 미소장
31 31 ] M. Ishii, Personal communication to R. Nelson, Los Alamos National Laboratory, 1987. 미소장

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