A Hexafluorobenzene Gamma Dosimeter For Use In Mixed Neutron And Gamma Fields PDF Download

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A Hexafluorobenzene Gamma Dosimeter for Use in Mixed Neutron and Gamma Fields

A Hexafluorobenzene Gamma Dosimeter for Use in Mixed Neutron and Gamma Fields
Author: G. D. Wait
Publisher:
Total Pages: 9
Release: 1968
Genre:
ISBN:

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A high-sensitivity dosimeter system to measure low gamma-ray dose rates in the presence of neutrons is discussed. The detector is a liquid scintillator that employs hexafluorobenzene (C6F6) as a solvent and is practically hydrogen free. The energy absorbed in the scintillator is determined directly by counting the analog-to-digital converter pulses of a multichannel analyzer in a fast scaler. A Monte Carlo computer program was written to determine the response of the scintillator to a broader range of gamma-ray energies. The response to fast neutrons also was measured and compared with calculations which showed that the major component in the neutron response was produced by beta( - ) decay following the (n, alpha) reaction in (19)F. (Author).


Development and Evaluation of a Neutron-gamma Mixed-field Dosimetry System Based on a Single Thermoluminescence Dosimeter

Development and Evaluation of a Neutron-gamma Mixed-field Dosimetry System Based on a Single Thermoluminescence Dosimeter
Author:
Publisher:
Total Pages: 84
Release: 1993
Genre:
ISBN:

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A neutron-gamma mixed-field dosimetry system based on a single lithium fluoride thermoluminescence dosimeter was developed. The system's ability to perform in the mixed neutron-gamma field of the lead/bismuth irradiation facility at the Ohio State University Research Reactor was then evaluated. Such a system is needed to gather accurate dosimetry data for radiobiology experiments which are performed in the lead/bismuth facility. The system was found to be inadequate for the purpose of measuring both dose components in the irradiation facility. In that environment, the system's response to the gamma radiation is obscured by the response to neutron radiation. A sensitivity analysis was performed to estimate the system's performance under different conditions, in order to determine the condition for which the system is useful for resolving both the gamma and the neutron components of the dose.


Accuracy of External Personnel Dosimetry Systems in Mixed Neutron and Gamma Radiation Fields

Accuracy of External Personnel Dosimetry Systems in Mixed Neutron and Gamma Radiation Fields
Author:
Publisher:
Total Pages:
Release: 1983
Genre:
ISBN:

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Estimates of biological effects associated with exposure to external radiation fields are generally based on the measured response of passive personnel dosimetry systems to the incident radiation. The increasing number of persons occupationally exposed to mixed neutron and gamma fields and recent questions concerning the relative biological hazards of different types of radiation have emphasized the need for accurate personnel radiation dose measurements. The performance characteristics of various neutron and gamma personnel dosimetry systems under actual mixed-field conditions have been determined. Analysis of the results indicates that significant inaccuracies can occur in neutron and gamma dose measurements in mixed radiation fields unless dosimeter performance and characteristics of the monitoring environment are considered in dosimeter evaluation. Neutron dose measurement accuracies could be improved by using dosimeters more suited to the anticipated radiation fields, calibrating dosimeters with sources appropriate for the energy spectra to be measured, applying correction factors to account for dosimeter performance in incident radiation fields, and standardizing the basis of reported dose equivalents. With regard to gamma monitoring, intercomparison results indicate that the selection of a basic dosimeter type which is relatively insensitive to neutrons is of great importance for accurate dose measurements in mixed fields.


Nuclear Science Abstracts

Nuclear Science Abstracts
Author:
Publisher:
Total Pages: 1142
Release: 1973
Genre: Nuclear energy
ISBN:

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