User's manual for ONEDANT: a code package for one-dimensional, diffusion-accelerated, neutral-particle transport

Abstract

1. Program Identification: ONEDANT 2. Computer for which Program is Designed: CDC-76OO, but the program has been implemented and run on tht IBM-370/190 and CRAY-I computers. 3. Function: 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. and eigenvalue search) problems subject to vacuum, reflective, perioaic, white, albedo, or inhomogeneous boundary flux conditions are solved. General anisotropic scattering is allowed and anisotropic inhomogeneous sources are permitted. 6. Running Time: Running time is directly related to problem size and to cen¬ tral processor and data transfer speeds. On the CDC-7600 a 70 energygroup, S ,, P-scatter, 40 space-point eigenvalue problem requires about A0 sec CPU time. A 42 energy-group, S_, P-scatter, 121 space-point fixed-source problem requires about 30 sec CPU time on the CDC-7600. A 1 energy-group, S,", P scatter, 307 space-point fixed-source problem requires from 2 to 3 sec CPU time on the CDC-7600. Generally, then, on the CDC-7600, the running times for ONEDANT will range from a few seconds to 1 or 2 minutes. 'I. Unvisual Features of the Program: The ONEDANT code package is modularly struc¬ tured in a form that separates the input and the output (or edit) func¬ tions from the main calculational (or solver) section of the code. The code makes use of binary, sequential data files,called interface files, io transmit data between modules and submodules. Standard interface files whose specifications have been defined by the Reactor Physics Committee on Computer Code Coordination are accepted, used, and cheated by the code. A totally new free-field card-image input capability is provided for the user. The code provides the user with considerable flexibility in using both card-image or sequential file input and also in controlling the execution of both modules and submodules. Separate versions of the code exist for short-word and long-word computers. 8. Programming Languages: The program is written in standard FORTRAN-IV language. 10. Material Available: Source deck (about 30 000 card-images), sample problems and this manual have been submitted to the Argonne Code Center and to the Radiation Shielding Information Center. viii I.

Benchmark tests on the Digital Equipment Corporation Alpha AXP 21164-based AlphaServer 8400, including a comparison of optimized vector and superscalar processing

“…This is true even when comparing CMOS microprocessor and vector implementations. TWODANT A two-dimensional discrete ordinates particle transport code used for neutral particle transport [9]. It includes a multigrid solver and is vectorizable to some extent.…”

RADTRAN 5 user guide.

“…The source was assigned an energy spectrum obtained from Oak Ridge National Laboratory calculations of the neutron flux at the surface of a lead-shielded spent fuel shipping cask. The neutron transport calculations were performed with the ONEDANT code, which solves the 1-D, multigroup, Boltzmann transport equation by the discrete ordinates method (O'Dell, 1982). The ENDF library, NJOY system, and ONEDANT code are discussed and evaluated for use in transportation analysis by Parks et al (1988).…”

First wall/blanket/shield design and optimization system

“…The second library was generated from VITAMIN-E [6] and KAOS/LIB-V [7] based on ENDF/B-V. The oneand two-dimensional discrete ordinates codes ONEDANT [8] and TWODANT [9] were employed for the transport calculations. BSDOS translates the engineering parameters of the FBS to input for the transport codes.…”