Applications of the Discrete ordinates of Oak ridge System (DOORS) package to Nuclear Engineering problems
Creators
- Azmy, Y.Y.1
- Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico (Mexico)
- Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico)
- Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)
- Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Mexico D.F. (Mexico)
- 1. The Pennsylvania State University, 229 Reber Building, University Park, PA 16802 (United States)
Description
Particle transport problems are notorious for their difficulty. This fact requires that production level computer codes designed to address realistic engineering problems possess three important features: (i) high computational efficiency as measured by solution accuracy for a fixed computational cost; (ii) a wide variety of options to enhance robustness of the transport solver; and (iii) a broad collection of support codes that extend the reach of the transport solver to a wide variety of applications. The Discrete Ordinates of Oak Ridge System (DOORS) code package was designed with these features in mind. In this paper, capabilities of member codes in the DOORS package are overviewed with particular emphasis on two newly developed peripheral codes: BOT3P the mesh-generation and visualization code package, and GipGui the graphical user interface for the cross section manipulation code, GIP. Two large applications are used to illustrate the tight coupling between the peripheral codes and the DORT and TORT transport solvers in two and three dimensional geometries, respectively. These are: (i) criticality calculations for the C5G7MOX core benchmark; and (ii) dose distribution calculations for the Target Service Cell (TSC) of the Spallation Neutron Source (SNS). (Author)
Availability note (English)
Available from INIS in electronic formFiles
36038712.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- Report number
- INIS-MX--1701
Conference
- Title
- 15. Annual Congress of the SNM; 22. Annual Meeting of the SMSR; International Joint Meeting Cancun 2004; International Conjunct Congress Cancun 2004; 2004 LAS/ANS Symposium
- Dates
- 11-14 Jul 2004
- Place
- Cancun (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 36038712
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; CROSS SECTIONS; D CODES; DESIGN; DIAGRAMS; DIMENSIONS; DISCRETE ORDINATE METHOD; EIGENVALUES; EXPERIMENTAL DATA; GEOMETRY; MEV RANGE 01-10; NUCLEAR ENGINEERING; OAK RIDGE; QUADRATURES; T CODES; TRANSPORT THEORY; USES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DATA; DEVELOPED COUNTRIES; ENERGY RANGE; ENGINEERING; INFORMATION; MATHEMATICS; MEV RANGE; NORTH AMERICA; NUMERICAL DATA; TENNESSEE; URBAN AREAS; USA