Radiation Protection Dosimetry · 2004 · 27 citations · 30 references
Electrical EngineeringEngineeringNuclear PhysicsMeasurementCalibrationMonte CarloNuclear SafetyNeutron SourceEducationWorkplace EnergyResponse CharacteristicsInstrumentationNeutron TransportNeutron ScatteringNuclear EngineeringPractical Implications
Improvements have been made to the Monte Carlo modelling used to calculate the response of the neutron survey instruments most commonly used in the UK, for neutron energies up to 20 MeV. The improved modelling of the devices includes the electronics and battery pack, allowing better calculations of both the energy and angle dependence of response. These data are used to calculate the response of the instruments in rotationally and fully isotropic, as well as unidirectional fields. Experimental measurements with radionuclide sources and monoenergetic neutron fields have been, and continue to be made, to test the calculated response characteristics. The enhancements to the calculations have involved simulation of the sensitivity of the response to variations in instrument manufacture, and will include the influence of the user and floor during measurements. The practical implications of the energy and angle dependence of response, variations in manufacture, and the influence of the user are assessed by folding the response characteristics with workplace energy and direction distributions.
30
MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister · 1993 · 5.1K citations
Engineering, Physics, Novice User +15
A new type of neutron spectrometer
R.L. Bramblett, Ronald I. Ewing, T. W. Bonner · Nuclear Instruments and Methods · 1960 · 529 citations
R. H. Olsher, Hsiao-Hua Hsu, A. Beverding et al. · Health Physics · 2000 · 185 citations