1. NAME AND TITLE OF DATA LIBRARY
FTF: Multigroup Neutron and Gamma-Ray Dose Transmission Factors for Concrete
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
No retrieval program is in the package.
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 Sn-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
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
8. DATA FORMAT AND COMPUTER
EBCDIC card images; IBM 360.
9. TYPICAL RUNNING TIME
No record of running time is available.
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
12. DATE OF ABSTRACT
KEYWORDS: RADIATION ENVIRONMENT; TRANSMISSION DATA