DIN 25483:2023-07: Methods of environmental monitoring using integrating solid-state dosimeters

This document shall be applied for the measurement of the long-term accumulated local dose generated by photon radiation with passive integrating dosemeters at installations and facilities where local dose measurements are to be performed within the framework of immission measurement programmes pursuant to Section 103(2) StrlSchV. In particular, this document specifies a procedure for monitoring the local gamma dose in accordance with the Guideline for Emission and Immission Monitoring of Nuclear Installations (REI) [2]. This document shall not be applied to installations or facilities for which the annual determination of the exposure of members of the public according to Section 101(2) StrlSchV is not required. Annex A to Annex F are non-normative and contain notes on the adaptation of the procedure in case of incidents, notes on the determination of the representative background dose, a calculation example by analytical means, notes on the application of the procedure for the measurement of neutron radiation, calculation examples with the Monte Carlo method as well as an example for the division of a dosimeter group. This document was prepared by the DIN Standards Committee for Materials Testing (NMP), Working Committee NA 062-07-63 AA "Radionuclide Laboratories". This document replaces DIN 25483:2000-09. Compared to DIN 25483:2000-09, the following changes have been made: (a) harmonisation of the terms and symbols with the international body of standards, in particular DIN EN ISO 11929-1, JCGM 200, IEC 62387; (b) generalisation of the procedure to all types of passive integrating dosimetry systems; (c) addition of a procedure for the determination of the additional dose; (d) consideration of the methodology for the determination of the characteristic limits according to the DIN EN ISO 11929 series of standards; e) updating of the procedural notes on the determination of a representative background dose; f) notes on the Monte Carlo calculation of the measurement uncertainty and characteristic limits included as Annex D; g) notes on the application of the procedure to neutron dosimetry included as Annex E; h) editorial revisions.