|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|NESC0184/01||IBM 370 series||IBM 370 series|
BRT1, like the original THERMOS code developed by H. Honeck of Brookhaven National Laboratory, computes the scalar thermal neutron spectrum as a function of position in a lattice by solving the integral transport equation with isotropic scattering. One-dimensional slab or cylindrical geometry may be used. As output the code supplies flux-averaged values of sigma a, sigma f, nu sigma f, sigma s, and d for the cell composition and the values of sigma a, sigma f, nu sigma f, sigma s, and sigma tr for the isotopic constituents.
The sample problem is a 2-region slab and is solved using 10 space points and 30 speed groups. There are two mixtures used. Five materials are used in the cell and one in the edit. The time in general is a function of the number of space points and energy groups used by the problem.
Typical running time for BRT1 with the random access library is one minute with a reflecting boundary condition and 30 seconds with a white boundary condition. Succeeding cases require approximately 15 seconds each.
In BRT1 options include the white boundary condition, current calculation, transverse buckling, linear anisotropic scattering correction, and smeared cell punched output for use as region input to a succeeding case. Random access library data can be stored on drum or disk.
|Package ID||Status date||Status|
|NESC0184/01||01-APR-1973||Tested at NEADB|
H.C. Honeck: A Thermalization Transport Theory Code for Reactor Lattice Calculations, BNL-5826 (September 1961).
H.C. Honeck: The Distribution of Thermal Neutrons in Space and Energy in Reactor Lattices Part 1 – Theory Nuclear Science and Engineering, p. 193 (1960).
D.R. Skeen and L.J. Page: THERMOS/Battelle..The Battelle Version of the THERMOS Code, BNWL-516 (June 1967).
|Package ID||Computer language|
|File name||File description||Records|
|NESC0184_01.001||RLITHE SOURCE PROGRAMME||494|
|NESC0184_01.002||RLITHE LIBRARY INPUT DATA||7450|
|NESC0184_01.003||BRT-1 SOURCE PROGRAMME||2571|
|NESC0184_01.004||BRT-1 JCL+OVERLAY CARDS+SAMPLE INPUT||39|
|NESC0184_01.005||RLITHE PRINT OUT OF THE LIBRARY||4968|
|NESC0184_01.006||BRT-1 SAMPLE OUTPUT||547|
Keywords: cross sections, cylinders, neutron spectra, one-dimensional, reactor lattices, scattering, slabs, thermal neutrons, transport theory.