Development And Evaluation Of A Neutron Gamma Mixed Field Dosimetry System Based On A Single Thermoluminescence Dosimeter PDF Download

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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.


Energy Research Abstracts

Energy Research Abstracts
Author:
Publisher:
Total Pages: 782
Release: 1995
Genre: Power resources
ISBN:

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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.


Neutron Contribution to CaF2

Neutron Contribution to CaF2
Author:
Publisher:
Total Pages: 38
Release: 2002
Genre:
ISBN:

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Thermoluminescent dosimeters (TLDs), particularly CaF2:Mn, are often used as photon dosimeters in mixed (n/[gamma]) field environments. In these mixed field environments, it is desirable to separate the photon response of a dosimeter from the neutron response. For passive dosimeters that measure an integral response, such as TLDs, the separation of the two components must be performed by post-experiment analysis because the TLD reading system cannot distinguish between photon and neutron produced response. Using a model of an aluminum-equilibrated TLD-400 chip, a systematic effort has been made to analytically determine the various components that contribute to the neutron response of a TLD reading. The calculations were performed for five measured reactor neutron spectra and one theoretical thermal neutron spectrum. The five measured reactor spectra all have dosimetry quality experimental values for aluminum-equilibrated TLD-400 chips. Calculations were used to determined the percentage of the total TLD response produced by neutron interactions in the TLD and aluminum equilibrator. These calculations will aid the Sandia National Laboratories-Radiation Metrology Laboratory (SNL-RML) in the interpretation of the uncertainty for TLD dosimetry measurements in the mixed field environments produced by SNL reactor facilities.


Optically Stimulated Luminescence Dosimetry

Optically Stimulated Luminescence Dosimetry
Author: L. Boetter-Jensen
Publisher: Elsevier
Total Pages: 375
Release: 2003-10-24
Genre: Science
ISBN: 008053807X

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Optically Stimulated Luminescence (OSL) has become the technique of choice for many areas of radiation dosimetry. The technique is finding widespread application in a variety of radiation dosimetry fields, including personal monitoring, environmental monitoring, retrospective dosimetry (including geological dating and accident dosimetry), space dosimetry, and many more. In this book we have attempted to synthesize the major advances in the field, covering both fundamental understanding and the many applications. The latter serve to demonstrate the success and popularity of OSL as a dosimetry method. The book is designed for researchers and radiation dosimetry practitioners alike. It delves into the detailed theory of the process from the point of view of stimulated relaxation phenomena, describing the energy storage and release processes phenomenologically and developing detailed mathematical descriptions to enable a quantitative understanding of the observed phenomena. The various stimulation modes (continuous wave, pulsed, or linear modulation) are introduced and compared. The properties of the most important synthetic OSL materials beginning with the dominant carbon-doped Al2O3, and moving through discussions of other, less-well studied but nevertheless important, or potentially important, materials. The OSL properties of the two most important natural OSL dosimetry material types, namely quartz and feldspars are discussed in depth. The applications chapters deal with the use of OSL in personal, environmental, medical and UV dosimetry, geological dating and retrospective dosimetry (accident dosimetry and dating). Finally the developments in instrumentation that have occurred over the past decade or more are described. The book will find use in those laboratories within academia, national institutes and the private sector where research and applications in radiation dosimetry using luminescence are being conducted. Potential readers include personnel involved in radiation protection practice and research, hospitals, nuclear power stations, radiation clean-up and remediation, food irradiation and materials processing, security monitoring, geological and archaeological dating, luminescence studies of minerals, etc.


Field Reader for a Combined Neutron-gamma Thermoluminescent Dosimeter

Field Reader for a Combined Neutron-gamma Thermoluminescent Dosimeter
Author: Canada. Dept. of National Defence. Research and Development Branch
Publisher: Research and Development Branch, Department of National Defence
Total Pages: 38
Release: 1977
Genre:
ISBN:

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An experimental model of a field reader to be used to interpret a combined neutron/gamma thermoluminescent dosimeter for military personnel has been designed and constructed. This instrument can operate from the 24-V battery of a military vehicle and can read dose to personnel in the range of 1 to 1000 rads. Satisfactory operation has been demonstrated and it has been shown no serious limitations on the accuracy of the dosimetry measurements are introduced by the reader. (Author).