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RSIC DATA LIBRARY DLC-130

1. NAME AND TITLE OF DATA LIBRARY

DABL69: Defense Nuclear Applications Broad-Group Library based on ENDF/B-V in ANISN Format.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM

BCBN: Convert ANISN card-image data to binary format.

3. CONTRIBUTOR

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

4. HISTORICAL BACKGROUND AND INFORMATION

This data package was developed to supersede the DLC-31/FEWG1 cross section library which has been used for Defense Nuclear Agency radiation transport calculations. The availability of ENDF/B-V data coupled with some evidence that the original group structure needed some refinement, provided the driving force in the development of a replacement for FEWG1 which is based on ENDF/B-IV.

The energy group structure (46n,23g) is a subset of the VITAMIN-E group structure and is tailored to air-over-ground environments.

5. APPLICATION OF THE DATA

Based on ENDF/B-V data and a reevaluation of Fe (MOD 3) which contains significant improvements, this library consists of 80 nuclides that can be used to solve typical calculations of interest to the DNA radiation transport community. Any computer code requiring multigroup cross sections can use the data.

6. SOURCE AND SCOPE OF DATA

Eighty materials from the DLC-113C/VITAMIN-E library which were available on October 30,1987 are included as a first part of the DABL69 library. These materials were collapsed using the AMPX code system with the VITAMIN-E weighting functions. The second part of the DABL69 library contains 8 additional materials including N-14, O-16, and steel using problem-dependent weighting functions generated by ANISN analysis of a typical problem. DABL69 contains 46 neutron and 23 gamma-ray energy groups. The Legendre order of expansion for angular distribution is 5.

As in DLC-31, the neutron groups are tailored to allow for the major peaks and valleys in the total neutron cross sections of nitrogen, oxygen, silicon, and iron. On the other hand, the gamma-ray groups are tailored to allow accurate calculation of pair production, annihilation photon transport, hydrogen capture, and backscatter photon transport. In the neutron energy range 0.2 to 1.8 MeV, additional boundaries were added to the parent DLC-31 group structure to give better resolution in the region where the largest fraction of the total kerma frequently occurs.

Source spectra and response functions useful in radiation transport applications are included in the library. Elemental kerma factors are provided for nuclides ranging from H-1 to Am-243.

Version A (D00130/I0360/00) includes card-image data files in both ANISN format and AMPX master format with kerma factor data derived from DLC-060/MACKLIB-IV.

Version B (D00130/I0360/01) is available in ANISN card images in wich the kerma factor data has been replaced with data derived from DLC-160/KAOS-LIB-V.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

BCBN will convert the data in ANISN format from card image to binary form. No input is required.

8. DATA FORMAT AND COMPUTER

Both ANISN and AMPX Card images; IBM 360/370. (D00130/I0360/00)

ANISN card images; All Computers. (D00130/I0360/01)

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

a. Included in documentation:

"Notes on Contents of DLC-130/DABL-69" (November 22, 1993).

D.T. Ingersoll, R.W. Roussin, C.Y. Fu, and J.E. White, "DABL69: A Broad-Group Neutron/Photon Cross-Section Library for Defense Nuclear Applications," ORNL/TM-10568 (June 1989).

b. Background information:

C.R. Weisbin, R.W. Roussin, J.J. Wagschal, J.E. White, and R.Q. Wright, "Vitamin-E: An ENDF/B-V Multigroup Cross Section Library for LMFBR Core and Shield, LWR Shield, Dosimetry and Fusion Blanket Technology," ORNL-5505 (ENDF-274) (1979).

Radiation Shielding Information Center Data Package DLC-113C/VITAMIN-E, "A Coupled 174-Neutron, 38-Gamma-ray Multigroup Cross-Section Library for Deriving Application-Dependent Working Libraries for Radiation Transport Calculations," contributed by Oak Ridge National Laboratory.

Radiation Shielding Information Center Data Package DLC-160/KAOS-LIB-V, "A Library of Nuclear Response Functions Generated by KAOS-V Code from ENDF/B-V and Other Data Files" (March 1991).

11. CONTENTS OF LIBRARY

Included is the referenced document and the cross sections and retrieval program transmitted on 1 cartridge tape in tar format or 10 DS/HD diskettes in self-extracting compressed DOS files (D00130/I0360/00) or (D00130/I0360/01) on two DS/HD diskettes in self-extracting compressed DOS files.

12. DATE OF ABSTRACT

August 1988, revised November 1988, September 1989, November 1993.

KEYWORDS: COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; ANISN FORMAT; NEUTRON CROSS SECTIONS; DETECTOR RESPONSE; MULTIGROUP CROSS SECTIONS; KERMA FACTORS