Field Reader For A Combined Neutron Gamma Thermoluminescent Dosimeter PDF Download
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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 | : |
Download Field Reader for a Combined Neutron-gamma Thermoluminescent Dosimeter Book in PDF, ePub and Kindle
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).
Author | : William D. Stepanek |
Publisher | : |
Total Pages | : 144 |
Release | : 1958 |
Genre | : Chemical dosimetry |
ISBN | : |
Download The Use of Chemical Dosimetry in Measuring a Combined Field of Gamma and Neutron Radiation Book in PDF, ePub and Kindle
Author | : |
Publisher | : |
Total Pages | : 84 |
Release | : 1993 |
Genre | : |
ISBN | : |
Download Development and Evaluation of a Neutron-gamma Mixed-field Dosimetry System Based on a Single Thermoluminescence Dosimeter Book in PDF, ePub and Kindle
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.
Author | : |
Publisher | : |
Total Pages | : 38 |
Release | : 2002 |
Genre | : |
ISBN | : |
Download Neutron Contribution to CaF2 Book in PDF, ePub and Kindle
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.
Author | : M. Oberhofer |
Publisher | : Springer Science & Business Media |
Total Pages | : 462 |
Release | : 1993-10-31 |
Genre | : Medical |
ISBN | : 9780792324362 |
Download Techniques and Management of Personnel Thermoluminescence Dosimetry Services Book in PDF, ePub and Kindle
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.
Author | : Kinga Enikö Kröbl |
Publisher | : |
Total Pages | : 184 |
Release | : 1999 |
Genre | : |
ISBN | : |
Download TLD-700 as Mixed (thermal Neutron-Gamma) Field Dosimeter Book in PDF, ePub and Kindle
Author | : Kevin Ryan Herminghuysen |
Publisher | : |
Total Pages | : 148 |
Release | : 1993 |
Genre | : |
ISBN | : |
Download Development and Evaluation of a Neutron-gamma Mixed-field Dosimetry System Based on a Single Thermoluminescence Dosimeter Book in PDF, ePub and Kindle
Author | : |
Publisher | : |
Total Pages | : 34 |
Release | : 1988 |
Genre | : |
ISBN | : |
Download Dose Equivalent LiF TLD (Thermoluminescent Dosimeter) Neutron and Photon Area Monitor Book in PDF, ePub and Kindle
A passive area monitor has been demonstrated that can measure neutron and gamma-ray dose equivalents. The Monitor combines the neutron moderator shield of a Snoopy remeter with a Lithium Fluoride TLD thermal neutron and gamma-ray detector. This area monitor can be a valuable aid in evaluating personnel LiF TLD albedo neutron dosimeter exposures. Calibrated with PuBe, the Monitor will read the actual neutron dose equivalent -60 + 160 percent over the neutron energy range from thermal to 14 MeV. Calibrated with Cobalt 60, the Monitor will read the actual gamma-ray dose equivalent from -40 to + 0 percent from 38 keV to Cobalt 60. Keywords: Radiation monitor, Photons, Remeter.
Author | : G. D. Wait |
Publisher | : |
Total Pages | : 9 |
Release | : 1968 |
Genre | : |
ISBN | : |
Download A Hexafluorobenzene Gamma Dosimeter for Use in Mixed Neutron and Gamma Fields Book in PDF, ePub and Kindle
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).
Author | : |
Publisher | : |
Total Pages | : 10 |
Release | : 1991 |
Genre | : |
ISBN | : |
Download Mixed Field Peronnel Dosimetry Book in PDF, ePub and Kindle
The high temperature peaks (TL peaks 6--7) of TLD-600 are known to have higher responses to high LET radiation than to low LET radiation. These high temperature peak characteristics were studied for the automatic reader-annealed Harshaw albedo neutron TLD. The high temperature peaks response is linear for neutrons over the dose equivalent range tested (0.05--3 mSv of a 252Cf source moderated by a 15 cm radius polyethylene sphere), but is supralinear above 20 mSv of 137Cs photons. The peaks ratio (peaks 6--7/peaks 3--5) of TLD-600 is 0.15 for neutrons of any incident energy, 0.01 for 137Cs gammas, and 0.02 for M-150 x-rays. Based on the high temperature peak characteristics, a mixed field neutron-photon personnel dosimetry methodology using a single TLD-600 element was developed. The dosimetric method was evaluated in mixed 238PuBe + 137Cs fields with four neutron-gamma dose equivalent ratios, and the neutron, photon and total dose equivalent estimations are better than 20% except in one case. However, it was found that the neutron and photon dose equivalent estimations are sensitive to the neutron and photon peaks ratios, depending on the neutron-photon dose equivalent ratio and the neutron source in the mixed field. Therefore, a successful use of this method requires knowledge of the photon and neutron energies in the mixed field. 13 refs., 6 figs., 2 tabs.