Advancements in generalized-geometry discrete ordinates transport for lattice physics calculations

PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics

Volumn 2006, Issue , 2006, Pages

  DeHart, Mark D ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

Arbitrary grid; Extended step characteristics; NEWT; SCALE; TRITON

Indexed keywords

COMPUTATIONAL GEOMETRY; COMPUTATIONAL METHODS; DISCRETE TIME CONTROL SYSTEMS; PROGRAM PROCESSORS;

ARBITRARY GRID; EXTENDED STEP CHARACTERISTICS; NEWT; SCALE; TRITON;

NUCLEAR PHYSICS;

EID: 33847216199     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (11)

1. M. D. DeHart, " NEWT: A new transport algorithm for two-dimensional discrete ordinates analysis in non-orthogonal geometries" Vol. II, Sect. F21 of SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, NUREG/CR-0200, Rev. 8 (ORNL/NUREG/CSD-2/R8), Vols. I, II, III (to be published in 2006).
2. M. D. DeHart, R. E. Pevey, AND T. A Parish, "An extended step characteristic method for solving the transport equation in general geometries," Nucl. Sci. Eng., 118, 79 (1994).
3. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, ORNL/TM-2005/39, Version 5, Vols. I- III (April 2005). Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725.
4. M. D. DeHart, "TRITON - A multidimensional depletion sequence for characterization of spent nuclear fuel" Vol. I, Sect. T1 of SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, NUREG/CR-0200, Rev. 8 (ORNL/NUREG/CSD-2/R8), Vols. I, II, III (to be published in 2006).
5. M. D. DeHart, Z. Zhong, and T. J. Downar, "TRITON: An advanced lattice code for MOX fuel calculations," Proc. of American Nuclear Society, Advances in Nuclear Fuel Management III, October 5-8, 2003, Hilton Head Island, SC, USA.
6. R. Roy, "The cyclic characteristics method," International Conference on the Physics of Nuclear Science and Technology, Long Island, New York, October 5-8, 1998.
7. M. Edenius, K. Ekberg, AND B. H. Forssen, "CASMO-4 - a fuel assembly burnup program - user's manual," Studsvik Report SOA-95/1, Studsvik of America (1995).
8. S. Santandrea, R. Sanchez, "Analysis and improvements of the DPN acceleration technique for the method of characteristics in unstructured meshes," Annals of Nuclear Energy 32, 163-193 (2005).
9. J. I. Hutton, New capabilities of the WIMS code, PHYSOR 2000, Pittsburgh, USA, Proceedings, ISBN 0-89448-655-1 (2000).
10. M. D. DeHart, "Lattice physics capabilities of the SCALE code system using TRITON," .. .this proceedings.
11. N transport for problem-dependent resonance self-shielding calculation," ANS 2005 Summer Meeting, San Diego, CA (June 2005).