Study of PHWR and BWR lattice benchmark problems with multigroup multidimensional neutron transport code dragon

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Neutron transport codes are an integral part of reactor physics calculation. The freely available lattice code DRAGON results from an effort to unify inside a single computer code various well-established numerical techniques and calculation methodologies which are commonly used to solve the neutron transport equation. It is of utmost importance for the user community, both from safety and operation point of view, that the codes being utilised for neutronic calculations maintain a high degree of confidence in their predictions. Benchmark problems are designed to test the capability of a neutronic code by comparing the results obtained from the code with well-established results, either from experimentation or from other validated neutronic codes. After PWRs, BWRs, and PHWRs are two of the most popular types of nuclear reactors currently in use worldwide. Consequently, the ability to perform accurate neutronic calculation involving these lattice types can be deemed as a necessary requirement in most modern lattice codes. In this work, we will study two benchmark problems based on the aforementioned reactor lattice types. Using the lattice code DRAGON and subsequently comparing the results with available published solutions, we aim to ascertain the capability of DRAGON to effectively simulate both of these two types of lattices with fresh and burnt fuel.

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  1. Askew JR, Fayers FJ, Kemshell PB (1966) A general description of the lattice code WIMS. J Brit Nucl Energy Soc 5:564–585

  2. Cupini E, De Matteis A, Simonini R (1980) KIM—a two-dimensional Monte Carlo program for thermal reactors. CNEN-RT/FIMA(80)2

  3. Draglib Download Page (2008) Polytechnique montréal, 26.05.2008. Accessed 04 Dec 2019

  4. Halsall MJ (1982) LWR-WIMS, a computer code for light water reactor lattice calculations. AEEW-R-1498, p 31, Winfrith, United Kingdom

  5. Hébert A (2014) DRAGON5 and DONJON5, the contribution of École Polytechnique de Montréal to the SALOME platform. In: Third Int. Conf. on physics and technology of reactors and applications (PHYTRA3), Tetouan, Morocco, May 12–14, 2014

  6. Hoffman A, Jeanpierre F, Kavenoky A, Livolant M, Henri L (1973) APOLLO—a multigroup code for the solution of the transport equation for thermal and fast neutrons. CEA-N-1610, Gif-sur-Yvette, Paris, France

  7. Huria HC (1978) MURLI—a multigroup integral transport theory code for thermal reactor lattice investigations. Atomkernenergi 31(2):87–95

  8. Hvidtfeldt L, Margrethe A (1973) RS: a code to produce multigroup neutron cross sections for reactor physics calculations, Risø National Laboratory (Risø-M; No. 1568), Roskilde, Denmark

  9. International Atomic Energy Agency (1996) In-core fuel management benchmarks for the PHWRs, IAEA-TECDOC-887, Vienna, Austria

  10. Kohler KE (2000) PostScript for technical drawings PSPLOT: a FORTRAN-callable PostScript plotting library user's manual. Nova Southeastern University, Oceanographic Centre, Dania.

  11. Krishnani PD (1982) CLUB—a multigroup integral transport theory code for analysis of cluster lattices. Ann Nucl Energy 9:255

  12. Lindstrøm Jensen KE (1970) Development and verification of nuclear calculation methods for light-water reactors," Risø National Laboratory (Risø-R-235), Roskilde, Denmark

  13. Maeder C, Wydler P (1984) International comparison calculations for a BWR lattice with adjacent gadolinium pins, NEACRP-L-271. Eidgenössisches Institut für Reaktorforschung (Federal Institute for Reactor Research), Würenlingen

  14. Marleau G, Hébert A (1991) Generalization of the Stamm’ler method for the self-shielding of resonant isotopes in arbitrary geometries. Nucl Sci Eng 108(3):230–239

  15. Marleau G, Hébert A, Roy R (1992) New computational methods used in the lattice code DRAGON. In: Topical meeting on advances in reactor physics, Charleston, South Carolina

  16. Marleau G, Roy R, Hébert A (1994) DRAGON: a collision probability transport code for cell and supercell. Technical report IGE-157, École Polytechnique de Montréal

  17. Marleau G, Hébert A, Roy R (2014) A user guide for DRAGON version 5. Technical report IGE-335, Ecole Polytechnique de Montréal

  18. Paratte JM, Foskolos K, Grimm P, Maeder C (1996) The PSI code system ELCOS for LWR core analysis. Paul Scherrer Institute, Villigen

  19. Peroni P, Ciarniello U (1982) Report CISE-1784

  20. Roy R (1994) The cyclic characteristics method. In: Int. Conf. physics of nuclear science and technology, Long Island, NY

  21. Roy R, Hébert A (2000) The GAN generalized driver. Technical report IGE-158, École Polytechnique de Montréal

  22. Saji E, Sakurai S, Takeda T (1981) Application of the response matrix method to BWR lattice analysis. Ann Nucl Energy 8(4):155–163

  23. Singh BS, Balakrishnan K, Balakrishnan MR (1980) RHEA—a five group neutronics code for burnup analysis of cluster geometry lattices, BARC/I-608. Bhabha Atomic Research Centre, Mumbai

  24. Tin ES, Loken PC (1979) POWDERPUFS-V physics manual, TDAI-31. AECL Engineering Company, Riyadh

  25. Tsuchihashi K, Hideki T, Kunihiki H, Yukio I, Kunio K, Toshiharu H (1983) SRAC: JAERI thermal reactor standard code system for reactor design and analysis. JAERI-1285, p 250

  26. Yamamoto M, Chiang RT, Congdon SP, Makino K, Mizuta H (1982) Validation of the TGBLA BWR bundle design methods. Trans Am Nucl Soc 43:698–699

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The authors would like to thank Dr. P. V. Varde, former Associate Director, Reactor Group and Shri C. G. Karhadkar, Associate Director, Reactor Group for their unfailing support and continuous encouragement.

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Correspondence to Shantanab Banerjee.

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Banerjee, S., Singh, T. Study of PHWR and BWR lattice benchmark problems with multigroup multidimensional neutron transport code dragon. Life Cycle Reliab Saf Eng (2020).

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  • Benchmark problem
  • Lattice code validation
  • DRAGON 5 code
  • Neutron transport