The Response of an Albedo Neutron Dosimeter to Moderated AmBe and 252(Cf) Neutron Sources.
Abstract
The response per Rem of an albedo neutron dosimeter has been determined for 56 neutron spectra which were generated by moderating AmBe and 252 Cf (Californium 252) neutron sources with various combinations of Lucite, polyethylene, and steel. The spectra were determined by using Bonner spheres and were further characterized by using commercially available 9-in., 3-in., and bare BF3 (Boron Fluoride) tube detectors and an Anderson-Braun-type Remmeter. The average energy of the spectra ranged from approximately 0.4 to 4.5 MeV. The ratio of the 3-in. detector response to the 9-in. detector response varied from about 0.3 to 3, and the ratio of the bare detector response varied from 0.04 to 3. The response per Rem of the albedo dosimeter, a 6 LiF-7 LiF ( Lithium Fluoride) detector pair behind a cadmium shield encased in a plastic badge, varied by more than a factor of seven. Our experiments showed that for this type albedo dosimeter, the bare to 9-in. detector ratio is more appropriate for reducing energy dependence than the 3-in. to 9-in. ratio, which is recommended for completely cadmium-encased albedo dosimeters, and is often used for other types of albedo dosimeters. Using both ratios gives optimum results; the average error due to energy dependence was reduced to about + or - 10%. Using the response ratio of a detector in front of the cadmium shield to the one behind the shield to correct for energy dependence was also effective for these spectra; the average error was approximately + or - 20%. Keywords: Personnel radiation monitoring; Radiation dosimetry; Neutrons. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Jul 23, 1985
- Accession Number
- ADA157457
Entities
People
- A. E. Nash
- G. H. Zeman
- G. I. Snyder
- G. K. Riel
- T. L. Johnson
Organizations
- United States Naval Research Laboratory