1. NAME AND TITLE OF DATA LIBRARY
CLAW-IV: Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections Based on ENDF/B-IV
for Radiation Transport Calculations.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
RESOLVE-B: Convert CLAW-IV activity tables into ANISN activity cross sections.
LIBGEN-B: Convert card-image FIDO formatted cross sections into unformatted ANISN
Los Alamos Scientific Laboratory, Los Alamos, New Mexico.
King Saud University, Riyadh, Saudi Arabia.
4. HISTORICAL BACKGROUND AND INFORMATION
Multigroup methods of solving the Boltzmann equation for neutron transport have been
implemented in a number of computer codes. Cross section input for these codes is traditionally in the
form of group-to-group transfer tables accompanied by an absorption cross section, a fission neutron
production cross, and a total cross section for each group. A useful variation of this format, known
as the coupled set, allows the simultaneous transport of neutrons and photons by treating the photon
energy groups as if they were the lowest energy neutron groups. This is because neutrons can
"downscatter" into the photon groups (photon production) but photons do not (appreciably) "upscatter"
into the neutron groups.
5. APPLICATION OF THE DATA
Coupled sets for a number of important materials have been produced by LaBauve and Seamon using data from ENDF/B-III and IV. CLAW-IV is intended as a replacement for those data sets and represents a marked improvement since there are many more materials and a much more complete set of response functions.
The library includes prompt and steady-state coupled sets for neutrons and photons in FIDO
format, prompt and steady-state fission spectra for the fissionable isotopes and a table of useful
response functions including heating and gas production.
6. SOURCE AND SCOPE OF DATA
The data in DLC-36D/CLAW-IV was prepared from ENDF/B-IV using the NJOY (PSR-118)
processing system. It consists of the following coupled 30 neutron, 12 gamma-ray group cross sections
where self-shielding is not important:
1H, 2H, 3H, 3He, 4He, 6Li, 7Li, 9Be, 10B, 11B, 12C, 14N, 16O, 19F, 23Na, Mg, 27Al, Si, Cl, K, Ca, Ti, V,
Cr, 55Mn, Fe, 59Co, Ni, Cu, Zirc2, 93Nb, Mo, 103Rh, 107Ag, 109Ag, Cd, 181Ta, W, 185Re, 187Re, 197Au,
Pb, 232Th, 233Pa, 233U, 234U, 235U, 236U, 237U, 238U, 239U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am,
243Am, 244Cm, 245Cm, 246Cm, 247Cm, 248Cm, 249Cf, 250Cf, 251Cf, 252Cf, stainless steel, concrete.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
Two retrieval programs have been added to DLC-036 D. LIGBEN-B converts the transport card-image FIDO cross sections into an unformatted ANISN library tape. RESOLVE-B lists or converts
the activity tables into ANISN cross section input formats (either formatted or unformatted). Options
for editing cross sections are provided in each program.
8. DATA FORMAT AND COMPUTER
Card images; IBM.
9. TYPICAL RUNNING TIME
The RESOLVE-B retrieval program executes in less than 5 cpu seconds on the IBM 3033.
T. A. Al-Kusayer, S. Sahin and A. Drira, "CLAW-B: Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections With Retrieval Programs For Radiation Transport Calculations," Unpublished Document, King Saud University, Riyadh, Saudi Arabia (1984).
R. J. Barrett and R. E. MacFarlane, "Coupled Neutron and Photon Cross Sections for Transport
Calculations," LA-7808-MS (April 1979).
11. CONTENTS OF LIBRARY
Included are the referenced documents and one (1.2MB) DOS diskette which contains the cross
sections and retrieval programs.
12. DATE OF ABSTRACT
November 1984, April 1988.
KEYWORDS: ANISN FORMAT; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS