Neutron kerma factors for tissue and particle detector materials from 15 to 150 MeV

Double differential (n, xp), (n, xd) cross sections of carbon and aluminum were measured for 65 and 75 MeV neutrons at angles between 12° and 70° using L::.E-E telescopes at a 7 Li(p, n) neutron source facility at TIARA. The data at 12° were obtained by employing an annular geometry. The telescopes consisting of SSD and NaI(Tl) scintillator, experimental methods and the data reduction procedures are presented as well as the results. The carbon data are compared favorably with existing experimental data. The (n, xp) spectra of both carbon and aluminum agreed fairly well with theoretical calculations based on the intra-nuclear cascade model and the multi-step Hauser-Feshbach model including preequilibrium effects, but the (n, xd) spectra differ significantly from those calculations.

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A consistent set of neutron kerma coefficients from thermal to 150 MeV for biologically important materials

Chadwick

Barschall

Caswell

et al. 1999

Medical Physics

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Neutron cross sections for nonelastic and elastic reactions on a range of elements have been evaluated for incident energies up to 150 MeV. These cross sections agree well with experimental cross section data for charged-particle production as well as neutron and photon production. Therefore they can be used to determine kerma coefficients for calculations of energy deposition by neutrons in matter. Methods used to evaluate the neutron cross sections above 20 MeV, using nuclear model calculations and experimental data, are described. Below 20 MeV, the evaluated cross sections from the ENDF/B-VI library are adopted. Comparisons are shown between the evaluated charged-particle production cross sections and measured data. Kerma coefficients are derived from the neutron cross sections, for major isotopes of H, C, N, O, Al, Si, P, Ca, Fe, Cu, W, Pb, and for ICRU-muscle, A-150 tissue-equivalent plastic, and other compounds important for treatment planning and dosimetry. Numerous comparisons are made between our kerma coefficients and experimental kerma coefficient data, to validate our results, and agreement is found to be good. An important quantity in neutron dosimetry is the kerma coefficient ratio of ICRU-muscle to A-150 plastic. When this ratio is calculated from our kerma coefficient data, and averaged over the neutron energy spectra for higher-energy clinical therapy beams [three p (68) + Be beams, and a d (48.5) + Be beam], a value of 0.94 +/- 0.03 is obtained. Kerma ratios for water to A-150 plastic, and carbon to oxygen, are also compared with measurements where available.

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Neutron kerma factors for tissue and particle detector materials from 15 to 150 MeV

Cited by 4 publications

References 33 publications

Assessment of neutron kerma coefficients and its calculation methodologies using recent basic ENDF-6 libraries

Assessment of neutron kerma coefficients and its calculation methodologies using recent basic ENDF-6 libraries

Measurements of (n,xp), (n,xd) Double Differential Cross Sections of Carbon and Aluminum for 65 and 75 MeV Neutrons

A consistent set of neutron kerma coefficients from thermal to 150 MeV for biologically important materials

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