Fast neutron dosimetry. Progress report, July 1, 1978-June 30, 1979. Wisconsin Medical Physics report No. WMP-109

Research activities relating to neutron dosimetry at the University of Wisconsin conducted between 1961 and 1979 are comprehensively reviewed. Former principal investigators discuss the activities and accomplishments which occurred during their tenure, and the current principal investigator discusses future plans. Seven reprints of papers dealing with specific aspects of the program are included in the report, but have not been indexed separately. (ERB

Energy imparted, energy transferred, and net energy transferred

The ICRU-defined non-stochastic quantity absorbed dose is related to the stochastic quantity energy imparted. In the present paper the corresponding stochastic quantities energy transferred and net energy transferred are defined as precursors for kerma and collision kerma, respectively. This forms a rational fundamental framework for radiation dosimetry which facilitates its teaching and understanding. For neutrons collision kerma coincides with kerma, because the heavy secondaries do not lose significant energy by radiative processes (e.g., bremsstrahlung)

Fast-neutron dosimetry. Progress report, 1 July 1982-30 June 1983

Several aspects of neutron and related photon radiological physics are being actively investigated. These research topics relate to measurement techniques, basic data values and theoretical discussions. In addition, a modest radiobiological effort is pursued concurrently. The unique coupled neutron/photon source provides an excellent tool for this latter work

Application of A150-plastic equivalent gases in microdosimetric measurements

Neutron dosimetry measurements with ionization chambers, for the most part, employ tissue equivalent plastic-walled cavities (Shonka A150) filled with either air or a methane-base tissue-like gas. The atomic composition of TE-gas and A150 plastic are not matched and are quite dissimilar from muscle. Awschalom and Attix (1980) have partially resolved the problem by formulating a novel A150-plastic equivalent gas. This establishes a homogeneous wall-gas cavity dosimeter for neutron measurements and confines the necessary corrections to the applications of kerma ratios. In this report, we present measurements of applications of two A150-plastic equivalent gases in a low pressure spherical proportional counter. Gas gains and alpha-particle resolutions were determined. For these A150-mixtures as well as a methane-based TE-gas and an Ar-CO/sub 2/ mixture, we report measurements of event size distributions from exposure to a beam of 14.8 MeV neutrons

Anti W comparisons for A150 plastic-equivalent gases, TE gas, and air

As part of our continuing evaluation of A150 plastic equivalent gases for neutron dosimetry, we have measured ionization ratios which are related to anti W ratios between gases in the p(66)Be(49) neutron beam at Fermilab. Additionally we have extended our earlier measurements (DeLuca, et al., 1980) at the UW gas target /sup 3/H(d,n)/sup 4/He neutron source to include an uncollimated beam geometry with ion chambers close to the target. Observed differences from the earlier results can probably be explained on the basis of neutron spectra, which await further determination