1. NAME AND TITLE OF DATA LIBRARY

FTF: Multigroup Neutron and Gamma-Ray Dose Transmission Factors for Concrete Slabs.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is in the package.

3. CONTRIBUTOR

Research Institute of National Defense, Stockholm, Sweden.

4. HISTORICAL BACKGROUND AND INFORMATION

The calculations described in FTF were initiated as a part of an effort to check out and make operable a code system for weapons radiation shielding of concrete buildings. Reliable neutron- and gamma-ray transmission data was needed which incorporated the most recent cross section information, especially on secondary gamma-ray production, and detailed information on the secondary gamma-ray dose in the range 0-15 cm penetration depth.

5. APPLICATION OF THE DATA

Calculations are given for an ordinary type of concrete. The gamma-ray, neutron- plus secondary gamma-ray and neutron only dose transmission factors resulting from the adjoint S_n-calculations are given in tables for slab thicknesses 3, 4, 5, 6, 7, 8, 10, 15. 20, 25, 30, 50, 75, 100 and 150 cm in a 40 group (22 neutron and 18 gamma) energy representation. The data are available on cards or on tape together with a retrieval and folding program. The transmission factors can be used with any source distribution.

6. SOURCE AND SCOPE OF DATA

A series of neutron- and gamma-ray dose transmission calculations are given for concrete infinite slabs with thickness up to 1.5 m. The calculations being of the adjoint type, the results can be used to find the transmitted gamma-ray dose from arbitrary incident gamma-ray sources as well as the transmitted neutron- and secondary gamma-ray dose from any incident neutron source distribution. Three sets of transmission factors are given: one for the gamma-ray dose, one for the neutron- plus secondary gamma-ray dose, and one for the neutron dose only. The description of a small retrieval and folding program is included. The program reads the data tables and the user's source information, performs the folding, and, if necessary, interpolates in slab thickness.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

EBCDIC card images; IBM 360.

9. TYPICAL RUNNING TIME

No record of running time is available.

10. REFERENCE

G. Engstrom and T. Lefvert, "Neutron- and Gamma-Ray Transport Calculations of Dose Transmission Factors in Concrete," C-20195-A2 (August 1977).

11. CONTENTS OF LIBRARY

Included are the referenced document and one (1.2MB) DOS diskette which contains the neutron- and gamma-ray dose transmission factors, the source program and the sample problem input and output.

12. DATE OF ABSTRACT

March 1985.