A least-squares technique for extracting neutron spectra from Bonner sphere data.
The accurate assessment of neutron flux and dose-rate levels in a medical environment is a topic of much current interest. In this paper, a least-squares data-analysis technique has been used for extracting neutron spectra and related information from Bonner sphere data. This technique, incorporated in the FORTRAN IV code NFLS is worthy of consideration as an alternative to the count-rate ratios and iterative-unfolding techniques used in the past. The analysis provides calculated total neutron flux density, dose-equivalent rate, and average and median-neutron-energy information as well as a plot of integral neutron-flux-density spectra. The method allows the calculation of the statistical uncertainty of each of the above quantities, which has not always been possible with other analytical methods. Results of calibration and experimental data analysis are presented and compared to results of the iterative-unfolding technique.
D003201:Computers; D004307:Dose-Response Relationship, Radiation; D004735:Energy Transfer; D008962:Models, Theoretical; D009502:Neutrons; D011834:Radiation Monitoring / Q000295:instrumentation / Q000379:methods*; D012588:Scintillation Counting; D013057:Spectrum Analysis