Styx: A multidimensional AMR SN scheme

Nuclear Science and Engineering

Volumn 143, Issue 3, 2003, Pages 281-290

  Aussourd, Christian ^a  

^a CEA DIF   (France)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTERS; GEOMETRY; INFORMATION ANALYSIS; MONTE CARLO METHODS; NEUTRONS; NUMERICAL ANALYSIS; PHASE SPACE METHODS; TOPOLOGY; TREES (MATHEMATICS);

ADAPTED MESH REFINEMENT (AMR);

PROBLEM SOLVING;

EID: 0037360586     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE03-A2336     Document Type: Article

References (15)

1. G. I. BELL and S. GLASSTONE, Nuclear Reactor Theory, Van Nostrand Reinhold Company (1970).
2. E. E. LEWIS and W. F. MILLER, Jr., Computational Methods of Neutron Transport, American Nuclear Society, La Grange Park, Illinois (1993).
3. M. J. BERGER and J. S. SALTZMANN, "AMR on the CM2,"Appl. Numer. Math., 14, 239, 253 (1994).
4. R. LÖHNER, "Mesh Adaptation in Fluid Mechanics," Eng. Fracture Mech., 50, 819, 847 (1995).
5. K. G. POWEL, "A Tree-Based Adaptive Scheme for the Solution of the Equations of Gas Dynamics and Magnetohydro-dynamics," Appl. Numer. Math., 14, 327, 352 (1994).
6. M. J. BERGER and P. COLLELA, "Local Adaptive Mesh Refinement for Hock Hydrodynamics," J. Comput. Phys., 82, 64, 84 (1989).
7. J. M. OWEN, J. VILLUMSEN, P. R. SHAPIRO, and H. MARTEL, "Adaptive Smooth Particle Hydrodynamics: Methodology II," Astrophys. J. (1996).
8. 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).
9. R. E. ALCOUFFE, R. S. BAKER, S. A. TURNER, and J. A. DAHL, "PARTISN," LA-CC 9862, Los Alamos National Laboratory (1998).
10. 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).
11. "MCNP™ - A General Monte Carlo N-Particle Transport Code," LA-12625-M, Version 4B, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (Mar. 1997).
12. N Code Styx," Proc. Mathematics and Computation (M & C '99), Madrid, Spain, September 1999, Vol. 2, p. 1205 (1999).
13. 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).
14. 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).
15. C. AUSSOURD, "Criticality Calculations of Prospera Reactor," Proc. Int. Mtg. Mathematical Methods for Nuclear Applications (M & C2001 ), Salt Lake City, Utah, September 2001, American Nuclear Society (2001) (CD-ROM).