Nuclear Engineering and Technology

  • 제37권6호
  • /
  • Pages.587-594
  • /
  • 2005
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

DEVELOPMENT OF MARS-GCR/V1 FOR THERMAL-HYDRAULIC SAFETY ANALYSIS OF GAS-COOLED REACTOR SYSTEMS

  • 발행 : 2005.12.01
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

In an effort to develop a thermal-hydraulic (TH) safety analysis code for Gas-cooled Reactors (GCRs), the MARS code, which was primarily developed for TH analysis of water reactor systems, has been extended here for application to GCRs. The modeling requirements of the system code were derived from a review of major processes and phenomena that are expected to occur during normal and accident conditions of GCRs. Models fur code improvement were then identified through a review of existing MARS code capability. Among these, the following priority models necessary fur the analysis of limiting high and low pressure conduction cooling events were evaluated and incorporated in MARS-GCR/V1 : 1) Helium (He) and Carbon Dioxide ($CO_2$) as main system fluids, 2) gas convection heat transfer, 3) radiation heat transfer, and 4) contact heat transfer models. Each model has been assessed using various conceptual problems for code-to-code benchmarks and it was demonstrated that MARS-GCR/V1 is capable of capturing the relevant phenomena. This paper describes the models implemented in MARS-GCR/V1 and their verification and validation results.

키워드

참고문헌

  1. Gas-Cooled Reactor Technical Working Group, Description and Evaluation of Candidate Gas-Cooled Reactor Systems, TWG-Summary Report XR-01-03 (2001)
  2. Gen-IV Technical Working Group 2, R&D Scope Report, Generation IV Nuclear Energy Systems Roadmap Technical Working Group 2 ？ Gas-Cooled Reactor System Concepts (2002)
  3. W.J. Lee, et al, Development of Realistic Thermal-Hydraulic System Analysis Code, KAERI/RR-2235/2001(2002)
  4. J.J. Jeong, K.S. Ha, B.D. Chung and W.J. Lee, 'MARS/MASTER Solution to OECD Main Steam Line Break Benchmark Exercise III', J. Korean Nuclear Society, 32, 214, (2000)
  5. K.D. Kim, et al., 'Development of a Nuclear Reactor Transient Analyzer Based on the Best-Estimate Codes, RETRAN and MARS', ANS Transactions, 89:813-1814, 2003 ANS Winter Meeting, New Orleans, US, November 16-20 (2003)
  6. B.D. Chung, S.W. Bae and Y.J. Lee, 'Development of Multidimensional Component, MULTID for Thermal Hydraulic System Analysis Code, MARS', KNS Fall Conference, Oct. 30 (2003)
  7. S.M. Lee, U.C. Lee, S.W. Bae and B.D. Chung, 'Assessment of MARS Multi-dimensional Two-phase Turbulent Flow Models for the Nuclear System Analysis', KNS Spring Conference, May. 27 (2005)
  8. S.M. Lee, U.C. Lee, S.W. Bae and B.D. Chung, 'Assessment of Multidimensional Flow Models in the System T/H Analysis Code MARS', NURETH-11, to be published (2005)
  9. NIST Standard Reference Database 12, NIST Thermodynamics and Transport Properties of Pure Fluids ？ NIST Pure Fluids, Version 5.0 (2000)
  10. H.C. Reynolds Jr., Internal Flow Reynolds Number Turbulent Heat Transfer, University of Arizona, EMMT Lab TR 2 (1968)
  11. W.J. Lee, Program GasProp, a Gas Property Generator, to be published (2005)
  12. V.D. Arp, R.D. McCarty, D.G. Friend, Thermophysical Properties of Helium-4 from 0.8 to 1500 K with Pressures of 2000 MPa, NIST Technical Note 1334, Bolder, CO (1998)
  13. V. Vesovic, W.A. Wakeham, G.A. Olchowy, S.V. Sengers, J.T.R. Watson and J. Millat, 'The Transport Properties of Carbon Dioxide', J. Phys. Chem. Ref. Data, 19, 3, pp. 763-808 (1990) https://doi.org/10.1063/1.555875
  14. $RELAP5-3D^{\copyright}$ Code Development Team $RELAP5-3D^{\copyright}$Code Manual, INEEL-EXT-98-00834, Revision 1.3 a, INEEL (2001)
  15. W. Williams, et al, Analysis of a Convection Loop for GFR Post-LOCA Decay Heat Removal from a Block-Type Core, MIT-ANP-TR-095 (2003)
  16. B. Metais, E.R.G. Eckert, 'Forced, Mixed and Free Convection Regimes', J. Heat Transfer, p. 295 (1964)
  17. T. Aicher, H. Martin, 'New Correlations for Mixed Turbulent Natural and Forced Convection Heat Transfer in Vertical Tubes', Int. J. Heat and Mass Transfer, 40, 15, p. 3617 (1997) https://doi.org/10.1016/S0017-9310(97)00026-4
  18. L.C. Burmeister, Convective Heat Transfer, 2nd Ed., John Wiley & Sons, Inc. (1993)
  19. V. Gnielinski, 'New Equations for Heat and Mass Transfer in Turbulent Pipe and Channel Flow', Int. Chem. Eng., 16,2, p. 359 (1976)
  20. D.A. Olson, Heat Transfer of Supercritical Carbon Dioxide Flowing in a Cooled Horizontal Tube, National Institute of Standards and Technology, NISTIR 6496 (2000)
  21. T.M. Hallman, Experimental study of combined forced and free convection in a vertical tube, NASA TN D-1104, December (1961)
  22. S.W. Churchill, Heat Exchanger Design Handbook, ed. Hewitt, G.F., Begell House, Inc., 1998
  23. S.W. Churchill and H.H.S. Chu, 'Correlating Equations for Laminar and Turbulent Free Convection From a Vertical Plate', Int. J. Heat and Mass Transfer, 18, p.1323 (1975) https://doi.org/10.1016/0017-9310(75)90243-4
  24. IAEA, Heat Transport and Afterheat Removal for Gas Cooled Reactors Under Accident Conditions, TECDOC-1163, Vienna, 64-103 (2000)