DocumentCode
2096668
Title
Design and Simulation of a Personnel Fast Neutron Dosimeter
Author
Ashfaq, Afshan ; Matiullah
Author_Institution
Pakistan Inst. of Eng. & Appl. Sci., Islamabad
fYear
2006
fDate
13-14 Nov. 2006
Firstpage
520
Lastpage
524
Abstract
A computer code NDOSEQ-60, written in FORTRAN 77, is presented. This code simulates the equivalent dose response of the electrochemically etched CR-39 based dosimeter to fast neutron in the energy range of 70 keV to 20 MeV. The code determines the response of the dosimeter consisting of CR-39 with up to five hydrogenous front radiators, as a function of neutron energy and angle of incidence. In the light of this code, a design of the energy and direction independent fast neutron dosimeter is proposed
Keywords
FORTRAN; digital simulation; dosimeters; nuclear engineering computing; solid-state nuclear track detectors; CR-39 based dosimeter; FORTRAN 77; NDOSEQ-60; hydrogenous front radiators; neutron energy; personnel fast neutron dosimeter; Algorithms; Assembly; Computational modeling; Computer simulation; Detectors; Etching; Neutrons; Particle scattering; Personnel; Protons;
fLanguage
English
Publisher
ieee
Conference_Titel
Emerging Technologies, 2006. ICET '06. International Conference on
Conference_Location
Peshawar
Print_ISBN
1-4244-0502-5
Electronic_ISBN
1-4244-0503-3
Type
conf
DOI
10.1109/ICET.2006.335913
Filename
4136881
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