Title
Primena detektora CR-39 u detekciji i dozimetriji neutrona
Creator
Milenković, Biljana, 1983-
Copyright date
2013
Object Links
Select license
Autorstvo 3.0 Srbija (CC BY 3.0)
License description
Dozvoljavate umnožavanje, distribuciju i javno saopštavanje dela, i prerade, ako se navede ime autora na način odredjen od strane autora ili davaoca licence, čak i u komercijalne svrhe. Ovo je najslobodnija od svih licenci. Osnovni opis Licence: http://creativecommons.org/licenses/by/3.0/rs/deed.sr_LATN Sadržaj ugovora u celini: http://creativecommons.org/licenses/by/3.0/rs/legalcode.sr-Latn
Language
Serbian
Cobiss-ID
Inventory ID
D-2663
Theses Type
Doktorska disertacija
description
datum odbrane: 18.11.2013.
Other responsibilities
mentor
Nikezić, Dragoslav
član komisije
Ciraj-Bjelac, Olivera, 1972-
član komisije
Krstić, Dragana
Academic Expertise
Prirodno-matematičke nauke
University
Univerzitet u Kragujevcu
Faculty
Prirodno-matematički fakultet
Group
Katedra Instituta za fiziku
Alternative title
Application of CR-39 detector in neutron detection and dosimetry
Publisher
Kragujevac : [B. Milenković],
Format
PDF/A (159 listova)
description
Prilozi.
Umnoženo za odbranu.
Univerzitet u Kragujevcu, Prirodno-matematički fakultet., 2013, dr fizičkih nauka.
Bibliografija : listovi 112-120.
Sažetak ;Summary.
Abstract (en)
A comparison of experimental and calculated responses of a CR-39 detector to neutron spectra from an Am–Be source is presented in this paper. A computer program called Neutron_CR-39.F90 for neutron simulation through a CR-39 detector and its detection was described and developed. The secondary particles are created in different directions and their latent tracks are oriented randomly within the detector. Some tracks will be etched from the point where the particle was created in the direction of the particle motion – this is direct etching. Other tracks will be etched from the point where the particle was stopped or from where it exited from the detector, in an opposite direction to the particle movement – this is the etching in a reverse direction. In this paper a calculation of the track
walls etched in the same and opposite directions is described by using Newton’s method. The program Neutron_CR-39.F90 contains subroutine Neutron.f90 for neutron simulation and subroutines Trackfdmsame.f90 and Trackfdmback.f90 for the calculation of created track profiles after detector etching in the same and reverse direction, respectively. Developed program has been used to calculate the neutron dose equivalent rate for the CR-39 detector as well as the track density. Conversion coefficient (sensitivity) between track density in
track/cm2 and neutron dose equivalent in mSv, was calculated by using above mentioned program. It has been found that sensitivity increases linearly with removed layer in the investigated range between 6 mm and 24 mm. The neutron equivalent dose rate was measured by an active device, and compared
with the calculated one. Good agreement was found between these two independent techniques for equivalent dose determination. The mean neutron fluence to dose equivalent conversion factor, hφ, was determined also, and it is in good agreement with previously published results (Burger and Schwaster, 1988; ISO/DIS 8529, 2000). Experimental and theoretical results, and their agreement, suggest the
potentiality of a CR-39 detector for fast neutron dosimetry.
Authors Key words
Neutroni
Classification
539.1.074.88(043.3)
Subject
Neutroni - Detektori
Type
monograph
manuscript text - theses
Text
Abstract (en)
A comparison of experimental and calculated responses of a CR-39 detector to neutron spectra from an Am–Be source is presented in this paper. A computer program called Neutron_CR-39.F90 for neutron simulation through a CR-39 detector and its detection was described and developed. The secondary particles are created in different directions and their latent tracks are oriented randomly within the detector. Some tracks will be etched from the point where the particle was created in the direction of the particle motion – this is direct etching. Other tracks will be etched from the point where the particle was stopped or from where it exited from the detector, in an opposite direction to the particle movement – this is the etching in a reverse direction. In this paper a calculation of the track
walls etched in the same and opposite directions is described by using Newton’s method. The program Neutron_CR-39.F90 contains subroutine Neutron.f90 for neutron simulation and subroutines Trackfdmsame.f90 and Trackfdmback.f90 for the calculation of created track profiles after detector etching in the same and reverse direction, respectively. Developed program has been used to calculate the neutron dose equivalent rate for the CR-39 detector as well as the track density. Conversion coefficient (sensitivity) between track density in
track/cm2 and neutron dose equivalent in mSv, was calculated by using above mentioned program. It has been found that sensitivity increases linearly with removed layer in the investigated range between 6 mm and 24 mm. The neutron equivalent dose rate was measured by an active device, and compared
with the calculated one. Good agreement was found between these two independent techniques for equivalent dose determination. The mean neutron fluence to dose equivalent conversion factor, hφ, was determined also, and it is in good agreement with previously published results (Burger and Schwaster, 1988; ISO/DIS 8529, 2000). Experimental and theoretical results, and their agreement, suggest the
potentiality of a CR-39 detector for fast neutron dosimetry.
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