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 ENDF/B.

(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.

3. CONTRIBUTORS

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, DOT,and MORSE.

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

Not applicable.

8. DATA FORMAT AND COMPUTER

BCD/EBCDIC card images; IBM 360/370.

9. TYPCAL RUNNING TIME

Not applicable.

10. REFERENCES

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 sections.

12. DATE OF ABSTRACT

November 1973; January 1987.