Nuclear Engineering and Technology

  • 제45권7호
  • /
  • Pages.951-960
  • /
  • 2013
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

A NOVEL APPROACH TO FIND OPTIMIZED NEUTRON ENERGY GROUP STRUCTURE IN MOX THERMAL LATTICES USING SWARM INTELLIGENCE

  • Akbari, M. (Faculty of Engineering, Shahid Beheshti University) ;
  • Khoshahval, F. (Faculty of Engineering, Shahid Beheshti University) ;
  • Minuchehr, A. (Faculty of Engineering, Shahid Beheshti University) ;
  • Zolfaghari, A. (Faculty of Engineering, Shahid Beheshti University)
  • 투고 : 2012.01.26
  • 심사 : 2013.08.01
  • 발행 : 2013.12.20
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

Energy group structure has a significant effect on the results of multigroup transport calculations. It is known that $UO_2-PuO_2$ (MOX) is a recently developed fuel which consumes recycled plutonium. For such fuel which contains various resonant nuclides, the selection of energy group structure is more crucial comparing to the $UO_2$ fuels. In this paper, in order to improve the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligence method is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used to generate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor and spectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy group structure. Calculations performed in four different types of $H_2O$ moderated $UO_2-PuO_2$ (MOX) lattices show that the optimized energy structure obtains more accurate results in comparison with the WIMS original structure.

키워드

참고문헌

  1. D.G. Cacuci, "Handbook of Nuclear Engineering", Springer Science Publications, Berlin, (2010).
  2. A. Pazirandeh, A. Tabesh, "New WIMS library generation from ENDF/B6 and effect of resonance group structure on cell parameters", J. of Nucl. Sci. and Technol. (Tokyo, Jpn.) (Suppl. 2), 900-903, (2002).
  3. J. Sanggene Han, "Sensitivity study on the energy group structure for high temperature reactor analysis", M.Sc. Thesis, the Pennsylvania State University, (2008).
  4. P. Mosca, C. Mounier, R. Sanchez, G. Arnaud, "An adaptive energy mesh constructor for multigroup library generation for transport codes", Nucl. Sci. Eng., 167 (1), 40-60, (2011). https://doi.org/10.13182/NSE10-10
  5. J.R. Askew, F.J. Fayers, and P.B. Kemshell, "A general description of the lattice code WIMS", Journal of the British Nuclear Energy Society (October), 564, (1996).
  6. R.J.J Stamm'ler and M.J Abbate, "Methods of Steady-State Reactor Physics in Nuclear Design", Academic Press, (1983).
  7. J. Kennedy and R. Eberhart, "Particle Swarm Optimization", Proceedings of IEEE International Conference on Neural Networks, IV. pp. 1942-1948, (1995).
  8. Winfrith, "LWR-WIMS, a Computer Code for Light Water Reactor Calculations", AEE, UK, AEEW-R 1498, (1982).
  9. MacFarlane and D.W. Muir, "The NJOY Nuclear Data Processing System, NJOY97.0 Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data", RSICC Code package PSR-368, (1998).
  10. R.D. Leamer, et al., "$PuO_2-UO_2$ Fueled Critical Experiments", Rep. WCAP 3726-1, Westinghouse Electric Corporation, Pittsburgh, PA, (1967).
  11. H. Tsuruta, et al., "Experiment and Calculation of keff for the Light-water Moderated Two-region Core of $UO_2$ and $PuO_2-UO_2$ Lattices", Rep. JAERI-M 4696, Japan Atomic Energy Research Institute, Tokai-mura (in Japanese), (1972).
  12. L.C. Schmid, R.C. Liikala, W.P. Stinson, and J.R. Worden, "Experiments with $PuO_2-UO_2$ Fuel Elements in Light Water", Physics Research Quarterly Rep. HW-81659, General Electric, Richland, WA, (1964).
  13. W.P. Stinson and J.H. Lauby, "Approach-to-critical Experiments with $UO_2$-4 wt% $PuO_2-H_2O$ Lattices in Plutonium", Utilization Program Technical Activities Quarterly Report, September-November 1968, Rep. BNWL-963, Pacific Northwest Laboratories, Richland, WA, (1969).
  14. J.F. Briesmeister, "MCNP4C User Manual", CCC-700, Oak Ridge National Library, (2000).
  15. R. Sher, S. Fiarman, "Studies of Thermal Reactor Benchmark Data Interpretation: Experimental Corrections", EPRI NP-209, October, (1976).
  16. M. Maucec and B. Glumac, "Thermal Lattice Benchmarks for Testing Basic Evaluated Data Files Developed with MCNP-4B", Jozef Stefan Institute, 3rd Regional Meeting: Nuclear Energy in Central Europe, (1996).
  17. N. A. Marks, "Installation and Validation of MCNP-4A", NTD/TN 200, Australian Nuclear Science and Technology Organization, (1997).
  18. WLUP, "WIMS-D library update: Final Report of a Coordinated Research Project", Vienna, International Atomic Energy Agency, (2007).
  19. R.C. Eberhart, P. Simpson, R. Dobbins, "Computational Intelligence PC Tools", Academic Press Professional, Massachussets, EUA, (1996).
  20. F. Khoshahval, A. Zolfaghari, H. Minuchehr, M. Sadighi, and A. Norouzi, "PWR fuel management optimization using continuous particle swarm intelligence", Ann. of Nucl. En. 37 (10), 1263-1271, (2010). https://doi.org/10.1016/j.anucene.2010.05.023