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Technical Paper

Styx: A Multidimensional AMR SN Scheme

Pages 281-290 | Published online: 10 Apr 2017

References

  • G.I. BELL and S. GLASSTONE, Nuclear Reactor Theory, VanNostrand Reinhold Company (1970).
  • E. E. LEWIS and W. F. MILLER, Jr., Computational Methods of Neutron Transport, American Nuclear Society, La Grange Park, Illinois (1993).
  • M. J. BERGER and J. S. SALTZMANN, “AMR on the CM2,” Appl. Numer. Math., 14, 239, 253 (1994).
  • R. LÖHNER, “Mesh Adaptation in Fluid Mechanics,” Eng. Fracture Mech., 50, 819, 847 (1995).
  • K. G. POWEL, “A Tree-Based Adaptive Scheme for the Solution of the Equations of Gas Dynamics and Magnetohydrodynamics,” Appl. Numer. Math., 14, 327, 352 (1994).
  • M. J. BERGER and P. COLLELA, “Local Adaptive Mesh Refinement for Hock Hydrodynamics,” J. Comput. Phys., 82, 64, 84 (1989).
  • J. M. OWEN, J. VILLUMSEN, P. R. SHAPIRO, and H. MARTEL, “Adaptive Smooth Particle Hydrodynamics: Methodology II,” Astrophys. J. (1996).
  • G. E. SJODEN and A. HAGHIGHAT, “PENTRAN: A Three-Dimensional Scalable Transport Code with Complete Phase-Space Decomposition,” Trans. Am. Nucl. Soc., 74, 181 (1996).
  • R. E. ALCOUFFE, R. S. BAKER, S. A. TURNER, and J. A. DAHL, “PARTISN,” LA-CC 9862, Los Alamos National Laboratory (1998).
  • C. AUSSOURD, “An Adapted DSN Scheme for Solving the Two-Dimensional Neutron Transport Equation on a Structured AMR Grid,” Proc. Int. Conf. Mathematical Methods and Supercomputing for Nuclear Applications, Saratoga Springs, New York, October 5-9, 1997, Vol. 1, p. 41, American Nuclear Society (1997).
  • “MCNPTM—A General Monte Carlo N-Particle Transport Code,” LA-12625-M, Version 4B, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (Mar. 1997).
  • C. AUSSOURD, “Latest Developments in the 2D-AMR SN Code Styx,” Proc. Mathematics and Computation (M&C ’99), Madrid, Spain, September 1999, Vol. 2, p. 1205 (1999).
  • C. AUSSOURD, “Styx 3D Implementation on SMP Architectures,” Proc. Int. Topl. Mtg. Advances in Reactor Physics and Mathematics and Computation into the Next Millenium (Physor 2000), Pittsburgh, Pennsylvania, May 7-12, 2000, American Nuclear Society (2000)(CD-ROM).
  • D. RIZ, “Calculation and Use of Multigroup Cross Sections Including Electron-Photon Cascade for a 3D Monte Carlo Neutron-Gamma Transport Code. Comparisons with MCNP-4B,” Proc. Int. Tpl. Mtg. Advances in Reactor Physics and Mathematics and Computation into the Next Millenium (Physor 2000), Pittsburgh, Pennsylvania, May 7-12, 2000, American Nuclear Society (2000)(CD-ROM).
  • C. AUSSOURD, “Criticality Calculations of Prospero Reactor,” Proc. Int. Mtg. Mathematical Methods for Nuclear Applications (M&C2001), Salt Lake City, Utah, September 2001, American Nuclear Society (2001)(CD-ROM).

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