User's manual for ONEDANT: a code package for one-dimensional, diffusion-accelerated, neutral-particle transport
ONEDANT is designed for the CDC-7600, but the program has been implemented and run on the IBM-370/190 and CRAY-I computers. ONEDANT solves the one-dimensional multigroup transport equation in plane, cylindrical, spherical, and two-angle plane geometries. Both regular and adjoint, inhomogeneous and homogeneous (k/sub eff/ and eigenvalue search) problems subject to vacuum, reflective, periodic, white, albedo, or inhomogeneous boundary flux conditions are solved. General anisotropic scattering is allowed and anisotropic inhomogeneous sources are permitted. ONEDANT numerically solves the one-dimensional, multigroup form of the neutral-particle, steady-state form of the Boltzmann transport equation. The discrete-ordinates approximation is used for treating the angular variation of the particle distribution and the diamond-difference scheme is used for phase space discretization. Negative fluxes are eliminated by a local set-to-zero-and-correct algorithm. A standard inner (within-group) iteration, outer (energy-group-dependent source) iteration technique is used. Both inner and outer iterations are accelerated using the diffusion synthetic acceleration method. (WHK)
- Research Organization:
- Los Alamos Scientific Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5226956
- Report Number(s):
- LA-9184-M; ON: DE82013745
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
654001* -- Radiation & Shielding Physics-- Radiation Physics
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73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BOLTZMANN EQUATION
COMPUTER CODES
DIFFERENTIAL EQUATIONS
DISCRETE ORDINATE METHOD
DOCUMENT TYPES
EQUATIONS
MANUALS
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
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O CODES
ONE-DIMENSIONAL CALCULATIONS
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73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BOLTZMANN EQUATION
COMPUTER CODES
DIFFERENTIAL EQUATIONS
DISCRETE ORDINATE METHOD
DOCUMENT TYPES
EQUATIONS
MANUALS
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
O CODES
ONE-DIMENSIONAL CALCULATIONS
PARTIAL DIFFERENTIAL EQUATIONS
RADIATION TRANSPORT
TRANSPORT THEORY