Mass optimization studies of gamma shield materials for space nuclear reactors
Creators
- 1. Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering
Description
A mass optimization study of the total shield mass requirements for gamma attenuation for a space nuclear power system is carried out. The reference system is a nuclear electric power-generating reactor with a 1016 γ/s source term and reference dimensions based on the Russian TOPAZ-II. Seven potential shield materials are analyzed, and the total gamma shield masses are presented for a desired dose equivalent of 5.0 mrem/h at the end of the shield. A three-dimensional shielding code, QAD-CGGP, is used to model the reactor and the truncated cone shield. Gamma energies of 0.5, 1.0, and 2.0 MeV are analyzed, and the required shield masses are normalized to the lowest value, giving a ''mass index.'' Comparison of the required masses and mass indices for both direct radiation and buildup dose is presented. For all three gamma energies, depleted uranium has a mass index of 1.0 and provides the required shielding with the lowest mass requirement. Mass indices between 1.2 and 1.7 are characteristic of tungsten and lead, making them potential substitutes for depleted uranium in the case of smaller reactor power levels
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 108
- Journal Issue
- 1
- Journal Page Range
- p. 126-136.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26021996
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BIOLOGICAL SHIELDS; COMPARATIVE EVALUATIONS; MASS; PHOTON TRANSPORT; SHIELDING MATERIALS; SPACE POWER REACTORS
- Descriptors DEC
- EVALUATION; MATERIALS; MOBILE REACTORS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION TRANSPORT; REACTORS; SHIELDS