Computer Programs
DLC-0013 ZZ-GARLIB.
last modified: 01-DEC-1973 | catalog | categories | new | search |

DLC-0013 ZZ-GARLIB.

ZZ GARLIB, Multigroup Resonance Cross-Section Group Constant Library for Tungsten and Depleted Pu

top ]
1. NAME

ZZ-GARLIB.

top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-GARLIB DLC-0013/01 Tested 01-DEC-1973

Machines used:

Package ID Orig. computer Test computer
DLC-0013/01 Many Computers Many Computers
top ]
3. DESCRIPTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
FORMAT: GAM-II

 

NUMBER OF GROUPS: 32-energy-group split (0.4 to 1234 eV).

 

NUCLIDES: tungsten (W,) and depleted uranium (U,) slabs

 

ORIGIN:

 

WEIGHTING SPECTRUM:

 

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The GARLIB data is produced by PSR-33/GAROL. Because other libraries of updated input data (i.e., resonance parameters and optimum energy point distributions) are required for PSR-33/GAROL, and the code is not widely used, the GARLIB data were generated for use by those designing space power reactor shields.

 

The 32-group, 0.4 to 1234 eV, capture and scattering cross sections contained in the library may be used as is for multigroup neutron transport calculations for the tabulated thicknesses of resonance absorber slabs (or cylindrical or spherical shells of the same thickness). They must, of course, be merged with a high energy (1 keV to 15 MeV) cross section set as calculated by GAM-II, for example. If the slab is not of the thickness listed, interpolated values may be used. Extrapolation, especially to thinner absorbers, is not advised because of the rapidly rising average cross sections. Total capture rates in the absorber will be preserved when these cross sections are used.

 

It is often inconvenient to perform a neutron transport calculation with the 32 energy groups in the 0.4 to 1234 eV region. For this reason, the relative group fluxes which were calculated by GAROL are also contained in the library to permit group collapsing. This group collapsing may be done by hand calculations or with the retrieval programs included with the data library.

 

Multigroup capture and scatter cross sections for the resolved resonance region were calculated for tungsten and depleted uranium slabs. The computer code used to generate the cross sections, PSR-33/GAROL, was previously observed to preserve the total capture rate in detailed multigroup neutron transport calculations. The cross sections are intended for use in shielding calculations of neutron transport and capture distribution in slabs or cylindrical or spherical shells of thick resonance absorbers.

 

Capture and scatter cross sections were obtained for fully dense tungsten and depleted uranium slabs of thickness 1, 2, 2.54, 4, and 8 centimeters; the slabs were surrounded by either hydrogen or lithium hydride. Group cross sections were calculated for a group split of 0.25 lethargy units extending from 0.414 to 1234.1 eV. This group structure is identical to that of the last 32 groups in the GAM-II 99-group structure; thus, the presently reported group cross section sets may be readily merged with the 1 keV to 15 MeV cross section data of GAM-II. All cross sections are microscopic and in units of barns. Because it may not be generally convenient to run with 32 energy groups in the 1 eV to 1 keV region, the group fluxes which were calculated with PSR-33/GAROL are also presented; further group collapsing either by hand calculations or with included computer codes is thus permitted.

 

Cross sections are included for: 180W, 182W, 183W, 184W, 186W, 235U and 238U.

 

Retrieval programs read multigroup region-averaged fluxes, capture cross sections, and scattering cross sections calculated and punched out by PSR-33/GAROL. Separate codes are included for the tungsten and uranium cases. The codes, when executed, will print out the information presented in the packaged documentation. The final section of each code outlines a procedure for further group-collapsing the cross sections.

 

The first code, GARW, manipulates isotopic tungsten cross sections. Tungsten is fully dense and isotope fractions are those occurring naturally. The second code, GARU, manipulates cross sections of uranium-238 and uranium-235 as calculated for fully dense depleted uranium (0.2% uranium-235).

top ]
6. TYPICAL RUNNING TIME

It takes approximately 1 minute to run either GARU or GARW on the IBM 7090 computer. On the IBM 360/91 computer, GARW runs in approximately 21 seconds and GARU in 18 seconds.

top ]
8. RELATED OR AUXILIARY PROGRAMS
  • GARW: A Program to Manipulate GAROL Resonance Cross Sections for Fully Dense Natural Tungsten.

  • GARU: A Program to Manipulate GAROL Resonance Cross Sections for Fully Dense Depleted Uranium.

top ]
9. STATUS
Package ID Status date Status
DLC-0013/01 01-DEC-1973 Tested at NEADB
top ]
10. REFERENCES
DLC-0013/01, included references:
- Gerald P. Lahti and Robert M. Westfall:
Multrigroup Resonance-Region Cross Sections for Tungsten and Depleted Uranium
for Use in Shielding Calculations
NASA TM X-1909 (January 1970)
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

National Aeronautics and Space Administration

Lewis Research Center

Cleveland, Ohio, USA

top ]
16. MATERIAL AVAILABLE
DLC-0013/01
File name File description Records
DLC0013_01.001 GARW SOURCE PROGRAM 147
DLC0013_01.002 GARLIB TUNGSTEN DATA 670
DLC0013_01.003 GARU SOURCE PROGRAM 136
DLC0013_01.004 GARLIB URANIUM DATA 370
DLC0013_01.005 GARW OUTPUT 1084
DLC0013_01.006 GARU OUTPUT 684
top ]
17. CATEGORIES
  • Z. Data

Keywords: capture, cross sections, data, multigroup, resonance, shielding, tungsten, uranium.