Personnel Dosimetry Systems For External Radiation Exposures PDF Download

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Techniques and Management of Personnel Thermoluminescence Dosimetry Services

Techniques and Management of Personnel Thermoluminescence Dosimetry Services
Author: M. Oberhofer
Publisher: Springer Science & Business Media
Total Pages: 462
Release: 1993-10-31
Genre: Medical
ISBN: 9780792324362

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The International Commission on Radiological Protection and the Euratom Council directive have specified that workers exposed to ionizing radiation shall be subjected to individual dose monitoring. In the past, individual doses have almost always been monitored by film badge dosimeters, but thermoluminescent dosimeters (TLDs) are now coming into widespread use, principally due to the availability of automated readout systems. Techniques and Management of Personnel Thermoluminescence Dosimetry Services gives details of the operation of and experience gained with a number of large-scale TL personnel dosimetry services, with particular attention being paid to the management aspects of such services. For technical and administrative personnel in TLD services, TLD system designers, staff of licensing authorities concerned with dosimetric licensing, students of radiation protection, especially in the area of protection from ionizing radiation. A basic knowledge of atomic and nuclear physics is assumed, and a training in radiation protection or health physics would be an advantage.


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.


Current Personnel Dosimetry Practices at DOE Facilities

Current Personnel Dosimetry Practices at DOE Facilities
Author:
Publisher:
Total Pages:
Release: 1981
Genre:
ISBN:

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Only three parameters were included in the personnel occupational exposure records by all facilities. These are employee name, social security number, and whole body dose. Approximate percentages of some other parameters included in the record systems are sex (50%), birthdate (90%), occupation (26%), previous employer radiation exposure (74%), etc. Statistical analysis of the data for such parameters as sex versus dose distribution, age versus dose distribution, cumulative lifetime dose, etc. was apparently seldom done. Less than 50% of the facilities reported having formal documentation for either the dosimeter, records system, or reader. Slightly greater than 50% of facilities reported having routine procedures in place. These are considered maximum percentages because some respondents considered computer codes as formal documentation. The repository receives data from DOE facilities regarding the (a) distribution of annual whole body doses, (b) significant internal depositions, and (c) individual doses upon termination. It is expected that numerous differences exist in the dose data submitted by the different facilities. Areas of significant differences would likely include the determination of non-measurable doses, the methods used to determine previous employer radiation dose, the methods of determining cumulative radiation dose, and assessment of internal doses. Undoubtedly, the accuracy of the different dosimetry systems, especially at low doses, is very important to the credibility of data summaries (e.g., man-rem) provided by the repository.