BS ISO 8529-1. Reference neutron radiations fields. Part 1. Characteristics and methods of production
17.240 - Radiation measurements
This document specifies the reference neutron fields, in the energy range from thermal up to 20 MeV, for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response as a function of neutron energy.
This document is concerned only with the methods of producing and characterizing the reference neutron radiation fields. The procedures for applying these radiation fields for calibrations are described in ISO 8529-2 and ISO 8529-3.
The reference neutron radiation fields specified are the following:
neutron fields from radionuclide sources, including neutron fields from sources in a moderator;
neutron fields produced by nuclear reactions with charged particles from accelerators;
neutron fields from reactors.
In view of the methods of production and use of them, these reference neutron radiation fields are divided, for the purposes of this document, into the following three separate sections.
In Clause 4, radionuclide neutron sources with wide spectra are specified for the calibration of neutron-measuring devices. These sources should be used by laboratories engaged in the routine calibration of neutron-measuring devices, the particular design of which has already been type tested.
In Clause 5, accelerator-produced monoenergetic neutrons and reactor-produced neutrons with wide or quasi monoenergetic spectra are specified for determining the response of neutron-measuring devices as a function of neutron energy. Since these reference neutron radiation fields are produced at specialized and well-equipped laboratories, only the minimum of experimental detail is given.
In Clause 6, thermal neutron fields are specified. These fields can be produced by moderated radionuclide sources, accelerators, or reactors.
For the conversion of neutron fluence into the quantities recommended for radiation protection purposes, conversion coefficients have been calculated based on the spectra presented in normative Annex A and using the fluence-to-dose-equivalent conversion coefficients as a function of neutron energy as given in ICRP Publication 74 and ICRU Report 57.
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