Abstract:
Following the computer programs for calculation of the dose- equivalent response of fast neutrons which have used for the development of a fast-neutron spectrometer. A computer program which is capable of calculating the dose-equivalent response of electrochemically etched (ECE) CR-39 detectors to thermal neutrons. The program, named IRFAN, is written in FORTRAN 77, and calculates the response of thermal neutron dosimeters consisting of CR-39 with type of (n,p) or (n,) converter screen. Depending upon the type of converter screen employed, the program takes into account the reaction products resulting from the (n,p) or (n,) reaction which generate tracks in the detector capable of being registered as ECE spots.
Page(s):
13-22
DOI:
DOI not available
Published:
Journal: Gomal University Journal of Research, Volume: 9, Issue: 1--2, Year: 1989