Nuclear Engineering and Technology

  • 제41권5호
  • /
  • Pages.677-690
  • /
  • 2009
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

CORE AND SUB-CHANNEL EVALUATION OF A THERMAL SCWR

  • Liu, Xiao-Jing (School of Nuclear Science and Engineering, Shanghai Jiao Tong University) ;
  • Cheng, Xu (School of Nuclear Science and Engineering, Shanghai Jiao Tong University)
  • 발행 : 2009.06.30
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

A previous study demonstrated that the two-row fuel assembly has much more favorable neutron-physical and thermal-hydraulic behavior than the conventional one-row fuel assemblies. Based on the newly developed two-row fuel assembly, an SCWR core is proposed and analyzed. The performance of the proposed core is investigated with 3-D coupled neutron-physical and thermal-hydraulic calculations. During the coupling procedure, the thermal-hydraulic behavior is analyzed using a sub-channel analysis code and the neutron-physical performance is computed with a 3-D diffusion code. This paper presents the main results achieved thus far related to the distribution of some neutronic and thermal-hydraulic parameters. It shows that with adjustment of the coolant and moderator mass flow in different assemblies, promising neutron-physical and thermal-hydraulic behavior of the SCWR core is achieved. A sensitivity study of the heat transfer correlation is also performed. Since the pin power in fuel assemblies can be non-uniform, a sub-channel analysis is necessary in order to investigate the detailed distribution of thermal-hydraulic parameters in the hottest fuel assembly. The sub-channel analysis is performed based on the bundle averaged parameters obtained with the core analysis. With the sub-channel analysis approach, more precise evaluation of the hot channel factor and maximum cladding surface temperature can be achieved. The difference in the results obtained with both the sub-channel analysis and the fuel assembly homogenized method confirms the importance of the sub-channel analysis.

키워드

참고문헌

  1. Y. Oka, “Review of High Temperature Water and Steam Cooled Reactor Concepts”, Proc. of SCR-2000, Tokyo, Japan, Nov.6-8, 2000
  2. A. Yamaji, K. Kamei, Y. Oka, et al, “Improved Core Design of the High Temperature Supercritical-Pressure Light Water Reactor”, Annals of Nuclear Energy, 32, 651 (2005) https://doi.org/10.1016/j.anucene.2004.12.006
  3. K. Kamei, A. Yamaji, Y. Ishiwatari, “Fuel and Core Design of Super LWR with Stainless Steel Cladding”, Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05), Seoul, Korea, May 15-19, 2005
  4. T. Schulenberg, J. Starflinger, J. Heinecke, “Three Pass Core Design Proposal for a High Performance Light Water Reactor”, Progress in Nuclear Energy, 50, 526(2008) https://doi.org/10.1016/j.pnucene.2007.11.038
  5. T. Schulenberg, and J. Starflinger, “European Research Project on High Performance Light Water Reactors”, $3^{rd}$ Int. Symposium on Supercritical Water-Cooled Reactors- Design and Technology, Shanghai, China, March 12-15, 2007
  6. X.J. Liu, X. Cheng, “Thermal-hydraulic and Neutronphysical and Characteristics of a New SCWR Fuel Assembly”, Annals of Nuclear Energy, 36, 28 (2009) https://doi.org/10.1016/j.anucene.2008.11.001
  7. X. Cheng, T. Schulenberg, D. Bittermann, P. Rau, “Design Analysis of Core Assemblies for Supercritical Pressure Conditions”, Nuclear Engineering and Design, 223(3), 279 (2003) https://doi.org/10.1016/S0029-5493(03)00059-1
  8. C. Waata, T. Schulenberg, X. Cheng, “Results of a Coupled Neutronics and thermal-hydraulics Analysis of a HPLWR Fuel Assembly”, Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05), Seoul, Korea, May 15-19, 2005
  9. A. Yamaji, T. Tanabe, Y. Oka, et al, “Evaluation of the Nominal Peak Cladding Surface Temperature of the Super LWR with Sub-channel Analyses”, Proceedings of GLOBAL 2005, Tsukuba, Japan, Oct 9-13, 2005
  10. X.J. Liu, X. Cheng, “Coupling Analysis on a New SCWR Core Design”, Proceedings of 2008 International Congress on Advances in Nuclear Power Plants (ICAPP '08), Anaheim, CA USA, June 8-12, 2008
  11. P. E. MacDonald, J. Buongiorno, J.W. Sterbentz, et al, “Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production”, INEEL/EXT-04-02530, Idaho National Engineering and Environmental Laboratory (2005)
  12. X. Cheng, T. Schulenberg, "Heat Transfer at Supercritical Pressures-Literature Review and Application to an HPLWR", FZKA 6609, Forschungszentrum Karlsruhe, (2001)
  13. M. J. Watts and C. T. Chou, “Mixed Convection Heat Transfer to Supercritical Pressure Water”, Proceedings of $7^{th}$ Int. Heat Transfer Conf., Munich, Germany, Sep. 6-12, 1982
  14. K. Rehme, “The Structure of Turbulence in Rod Bundles and the Implications on Natural Mixing between the Subchannels,” Int. Journal of Heat and Mass Transfer, 35, 567 (1992) https://doi.org/10.1016/0017-9310(92)90291-Y