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Energy dependence of metallic-encapsulated thermoluminescent dosimeters. Annual report

Technical Report ·
DOI:https://doi.org/10.2172/5180142· OSTI ID:5180142
The gamma-ray energy responses of encapsulated /sup 7/LiF and CaF/sub 2/:Mn thermoluminescent dosimeters were measured and compred to calculated values. This study was performed in order to improve the accuracy of gamma-ray heating measurements made in polyenergetic gamma-ray fields such as Argonne National Laboratory's Zero Power Reactors. Equations used in the development of the TERC/III computer code and code input parameters are specified. A section on TLD precision is also included. Comparisons between calculations and experiments are reported for a gamma-ray energy range of 0.122 to 1.33 MeV and encasement media with a range of atomic numbers from 13 to 82.
Research Organization:
Kansas State Univ., Manhattan (USA). Dept. of Nuclear Engineering
DOE Contract Number:
AS02-78ET37239
OSTI ID:
5180142
Report Number(s):
DOE/ET/37239-1
Country of Publication:
United States
Language:
English