Published December 27, 1995 | Version v1
Miscellaneous

DNTM/R2D, 2-D Transport in X-Y Geometry

Description

1 - Description of program or function: DNTM/R2D solves the neutron transport equation in two-dimensional X-Y geometry by the discrete nodal transport method. Source and eigenvalue problems can be solved. As compared to the two-dimensional nodal transport code DNTM/2D, the following new improved features are included: - Anisotropic scattering is considered. The order of anisotropic scattering is from P0 to P3. - The cross section input format is the same as for ANISN. Multi- group cross section libraries such as DLC-37 and DLC-BUGLE-80 can be used. 2 - Method of solution: DNTM/R2D uses the discrete nodal transport method. Anisotropic scattering is treated using Legendre expansion. Order of interior flux approximation is 2. Plane leakage approximation of surface flux is used. 3 - Restrictions on the complexity of the problem: Maximum number of: anisotropic scattering order = 3; material composition = 20; energy groups = 2; angular quadrature = 8; zones = 30. When coarse-mesh re-balancing is used, the maximum number of coarse meshes is 12 in each direction. If the computer permits some arrays can be enlarged to reduce the above restrictions.

Additional details

Identifiers

Publishing Information

Imprint Pagination
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INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39105805
Subject category
S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Computer Program Description, Non-conventional Literature
Descriptors DEI
ANISOTROPY; APPROXIMATIONS; COMPUTER PROGRAM DOCUMENTATION; CROSS SECTIONS; D CODES; EIGENVALUES; GEOMETRY; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; SCATTERING; TWO-DIMENSIONAL CALCULATIONS; WEBSITES
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; DOCUMENT TYPES; MATHEMATICS; TRANSPORT THEORY