1. NAME AND TITLE OF DATA LIBRARY
BP: Data for Selected Shielding Benchmark Problems Specified in ORNL-RSIC-25,
Shielding Benchmark Problems.
(A) BP 3.0 - 22 Neutron, 18 Gamma-Ray Group Cross Sections for Air, Generated by CSP from
(B) BP 6.0 - 22 Neutron, 18 Gamma-Ray Group Cross Sections for H, 10B, and 12C, Generated by
SUPERTOG and ANISN from ENDF/B.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM
No retrieval program is included in the package.
Oak Ridge National Laboratory, Oak Ridge, Tennessee.
Science Applications, Inc., Albuquerque, New Mexico.
4. HISTORICAL BACKGROUND AND INFORMATION
The data in DLC-8 are those used by contributors to the benchmark problem solutions published
in ORNL-RSIC-25 (ANS-SD-9), Shielding Benchmark Problems. The publication is a joint effort of
the American Nuclear Society Radiation Protection and Shielding Division, the ANS-6 Shielding
Benchmark Problems Group, and the Radiation Shielding Information Center. Where possible, RSIC
has acquired the actual data used and packaged them in DLC-8/BP.
5. APPLICATION OF THE DATA
The cross section data can be used to repeat the Shielding Benchmark Problems 3.0 and 6.0 for
testing against the results published in ORNL-RSIC-25.
6. SOURCE AND SCOPE OF DATA
DLC-8A/BP-3: Neutron cross sections from the CCC-17/O5R library were processed into 104
neutron groups using the PSR-9/CSP code. The fine-group neutron cross sections were collapsed to
22 broad groups using CCC-254/ANISN with an equilibrium fission spectrum source. The resulting
multigroup cross sections are P5 coefficients punched on cards in format suitable for input to ANISN,
DLC-8B/BP-6: The neutron and gamma-ray cross sections for 12C, H, and 10B were from ENDF/B-II data. The neutron multigroup cross sections were generated into 104 neutron groups using the
PSR-13/SUPERTOG code. The fine-group neutron cross sections were collapsed to 22 broad groups
using CCC-254/ANISN with an equilibrium fission spectrum source. The gamma-ray multigroup
cross sections were generated using PSR-7/MUG. The neutron-gamma-ray coupling utilized yield data
from the DLC-12/POPOP4 library (data sets 010101, 060101, 060301, and 05100201). The neutron-gamma-ray coupled multigroup cross-section set was generated using the SAMPLE COUPLING
CODE (ASCC). The multigroup cross sections are in a 22-18 group structure with P3 coefficients
punched on cards in format suitable for input to ANISN, DOT, and MORSE.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
BCD/EBCDIC card images; IBM 360/370.
9. TYPCAL RUNNING TIME
E. A. Straker, "SHIELDING BENCHMARK PROBLEM 3.0: Neutron Spectrum from Point Fission and 14 MeV Sources in Infinite Air," from ORNL-RSIC-25 (December 1968).
C. E. Burgart, "SHIELDING BENCHMARK PROBLEM 6.0: Neutron and Gamma-Ray Fluence
Transmitted through a Slab of Borated Polyethylene," from ORNL-RSIC-25 (December 1973).
11. CONTENTS OF LIBRARY
Included are the referenced documents and one tape cartridge in TAR format which contains cross
12. DATE OF ABSTRACT
November 1973; January 1987.
KEYWORDS: AIR CROSS SECTIONS; ANISN FORMAT; BENCHMARK PROBLEM CROSS SECTIONS; COUPLED NEUTRON-GAMMA-RAY CROSS SECTIONS; MULTIGROUP CROSS SECTIONS; POLYETHYLENE CROSS SECTIONS