Abstract
1. In this work we have made attempts to: - analyze the problems of reactor radiation dosimetry; - describe the solutions of this problem by the calorimetric method; - present our results of measurements of the reactor RA at Vinca, and to describe the method, apparatus and measuring equipment used. 2. Use was made of the isothermal calorimeter with thermistors which measured the absorbed dose rates within the range 10{sup 4}-10{sup 6} rad/h, with an accuracy of 2-5%. It was shown that the reactor radiation in which the thermal neutron flux is up to the order of magnitude 10{sup 12} n/cm{sup 2}/sec, and the integral thermal neutron flux up to about 10{sup 16} n/cm{sup 2} exerts no significant influence upon the working characteristics out of the thermistors used. 3. Determination was made of the absorbed dose distribution into the gamma-ray and the neutron contribution. For this purpose we used 3 materials: ordinary water, heavy water and graphite. 4. Measurements were carried out in two vertical experimental holes 'VK-5' and 'VK-6' of the reactor RA at several heights. It has been shown that the absorbed dose height distribution agrees well with the thermal flux distribution curve, although the relations of the
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Radak, B;
Markovic, V;
Draganic, I
[1]
- Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)
Citation Formats
Radak, B, Markovic, V, and Draganic, I.
Radiation dosimetry of the reactor RA at Vinca, Measurements by isothermal calorimeter.
Serbia and Montenegro: N. p.,
1961.
Web.
Radak, B, Markovic, V, & Draganic, I.
Radiation dosimetry of the reactor RA at Vinca, Measurements by isothermal calorimeter.
Serbia and Montenegro.
Radak, B, Markovic, V, and Draganic, I.
1961.
"Radiation dosimetry of the reactor RA at Vinca, Measurements by isothermal calorimeter."
Serbia and Montenegro.
@misc{etde_20871697,
title = {Radiation dosimetry of the reactor RA at Vinca, Measurements by isothermal calorimeter}
author = {Radak, B, Markovic, V, and Draganic, I}
abstractNote = {1. In this work we have made attempts to: - analyze the problems of reactor radiation dosimetry; - describe the solutions of this problem by the calorimetric method; - present our results of measurements of the reactor RA at Vinca, and to describe the method, apparatus and measuring equipment used. 2. Use was made of the isothermal calorimeter with thermistors which measured the absorbed dose rates within the range 10{sup 4}-10{sup 6} rad/h, with an accuracy of 2-5%. It was shown that the reactor radiation in which the thermal neutron flux is up to the order of magnitude 10{sup 12} n/cm{sup 2}/sec, and the integral thermal neutron flux up to about 10{sup 16} n/cm{sup 2} exerts no significant influence upon the working characteristics out of the thermistors used. 3. Determination was made of the absorbed dose distribution into the gamma-ray and the neutron contribution. For this purpose we used 3 materials: ordinary water, heavy water and graphite. 4. Measurements were carried out in two vertical experimental holes 'VK-5' and 'VK-6' of the reactor RA at several heights. It has been shown that the absorbed dose height distribution agrees well with the thermal flux distribution curve, although the relations of the absorbed doses of the two holes are not in accordance with the corresponding thermal flux relations (author)}
place = {Serbia and Montenegro}
year = {1961}
month = {Dec}
}
title = {Radiation dosimetry of the reactor RA at Vinca, Measurements by isothermal calorimeter}
author = {Radak, B, Markovic, V, and Draganic, I}
abstractNote = {1. In this work we have made attempts to: - analyze the problems of reactor radiation dosimetry; - describe the solutions of this problem by the calorimetric method; - present our results of measurements of the reactor RA at Vinca, and to describe the method, apparatus and measuring equipment used. 2. Use was made of the isothermal calorimeter with thermistors which measured the absorbed dose rates within the range 10{sup 4}-10{sup 6} rad/h, with an accuracy of 2-5%. It was shown that the reactor radiation in which the thermal neutron flux is up to the order of magnitude 10{sup 12} n/cm{sup 2}/sec, and the integral thermal neutron flux up to about 10{sup 16} n/cm{sup 2} exerts no significant influence upon the working characteristics out of the thermistors used. 3. Determination was made of the absorbed dose distribution into the gamma-ray and the neutron contribution. For this purpose we used 3 materials: ordinary water, heavy water and graphite. 4. Measurements were carried out in two vertical experimental holes 'VK-5' and 'VK-6' of the reactor RA at several heights. It has been shown that the absorbed dose height distribution agrees well with the thermal flux distribution curve, although the relations of the absorbed doses of the two holes are not in accordance with the corresponding thermal flux relations (author)}
place = {Serbia and Montenegro}
year = {1961}
month = {Dec}
}