ANISN-L, a CDC-7600 code which solves the one-dimensional, multigroup, time dependent transport equation by the method of discrete ordinates
The code ANISN-L solves the one-dimensional, multigroup, time-independent Boltzmann transport equation by the method of discrete ordinates. In problems involving a fissionable system, it can calculate the system multiplication or alpha. In such cases, it is also capable of determining isotopic concentrations, radii, zone widths, or buckling in order to achieve a given multiplication or alpha. The code may also calculate fluxes caused by a specified fixed source. Neutron, gamma, and coupled neutron--gamma problems may be solved in either the forward or adjoint (backward) modes. Cross sections describing upscatter, as well as the usual downscatter, may be employed. This report describes the use of ANISN-L; this is a revised version of ANISN which handles both large and small problems efficiently on CDC-7600 computers. (RWR)
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 7189832
- Report Number(s):
- UCID-17106; TRN: 76-016753
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BOLTZMANN EQUATION
NUMERICAL SOLUTION
COMPUTER CODES
A CODES
GAMMA TRANSPORT THEORY
NEUTRON TRANSPORT THEORY
CDC COMPUTERS
DISCRETE ORDINATE METHOD
MULTIGROUP THEORY
NEUTRON FLUX
ONE-DIMENSIONAL CALCULATIONS
COMPUTERS
DIFFERENTIAL EQUATIONS
EQUATIONS
RADIATION FLUX
TRANSPORT THEORY
654003* - Radiation & Shielding Physics- Neutron Interactions with Matter
654001 - Radiation & Shielding Physics- Radiation Physics
Shielding Calculations & Experiments