Nuclear Engineering and Technology

  • 제34권3호
  • /
  • Pages.250-258
  • /
  • 2002
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculations

  • 발행 : 2002.06.01
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

This Paper is to apply the well-established coarse mesh finite difference(CMFD) method to the method of characteristics(MOC) transport calculation as an acceleration scheme. The CMFD problem is first formulated at the pin-cell level with the multi-group structure To solve the cell- based multi-group CMFD problem efficiently, a two-group CMFD formulation is also derived from the multi-group CMFD formulation. The performance of the CMFD acceleration is examined for three test problems with different sizes including a realistic quarter core PWR problem. The CMFD formulation provides a significant reduction in the number of ray tracings and thus only about 9 ray tracing iterations are enough for the realistic problem. In computing time, the CMFD accelerated case is about two or three times faster than the coarse-mesh rebalancing(CMR) accelerated case.

키워드

참고문헌

  1. G. S. Lee, N. J. Cho and S. G. Hong, 'Acceleration and Parallelization of the Method of Characteristics for Lattice and Whole-Core Heterogeneous Calculation,' ANS Int. Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the next Millennium, PHYSOR 2000, Pittsburgh, Pennsylvania, May 7-12(2000)
  2. S. Kosaka and E. Saji, 'The Characteristics Transport Calculation for a Multi-Assembly System using Neutron Path Linking Technique,' Proc. Int. Conf. Math. and Comp., Reactor Physics and Environmental Analysis in Nuclear Applications, p. 1890, Madrid, Spain, Sep. 27-30(1999)
  3. H. G. Joo, G. Jiang and T. J. Downar, 'Stabilization Techniques for the Nonlinear Analytic Nodal Method,' Nucl. Sci. Eng, 130, 47(1998) https://doi.org/10.13182/NSE98-A1988
  4. Y. A. Chao, 'Coarse Mesh Finite Difference Methods and Applications,' ANS Int. Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the next Millennium, PHYSOR 2000, Pittsburgh, Pennsylvania, May 7-12(2000)
  5. K. S. Smith and J. D. Rhodes III, 'CASMO Characteristics Methods for Twp-Dimensional PWR and BWR Core Calculations,' Trans. Am. Nucl. Soc, Winter Mtg., Washington D. C, 294-296(2000)
  6. M. J. Halsall, 'CACTUS, A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries,' AEEW-R-1291, United Kingdom Atomic Energy Authority, Winfrith(1980)
  7. A. Leonard, C. T. McDaniel, 'Optimal Polar Angles and Weights, for the Characteristics Method,' Trans. Am. Nucl. Soc, 73, 172(1995)
  8. H. G. Joo et. al., 'One-Node Solution Based Nonlinear Analytic Nodal Method,' Proceedings of the Korean Nuclear Society Autumn Meeting., Pohang, Korea, May 26-27(2000)
  9. H. G. Joo, J. Y. Cho, J. S. Song, and S. Q. Zee, 'Multigroup Transient Calculation within the Framework of a Two-Group Hexagonal CMFD Formulation,' The '2001 ANS. Mtg. Math. Method. Nucl. Appl., Salt Lake City, UT, Sept. 9-13(2001)
  10. N. Z. Cho, 'Benchmark Problems in Reactor and Particle Transport Physics,' available on internet (http://nurapt.kaist.ac.kr/benchmark >) (June 2000)