Loading…

Improvement of $^{93m}$Nb and $^{93m}$Rh activity measurement methodology for reactor dosimetry

Reactor dosimetry is based on the analysis of the activity of irradiated dosimeters, such as $^{93m}$Nb and $^{103m}$Rh. The activity measurement of these dosimeters is conventionally performed by X-ray spectrometry, but the low-energy of emitted photons makes it difficult to derive reliable results...

Full description

Saved in:
Bibliographic Details
Main Authors: Riffaud, Jonathan, Lépy, Marie-Christine, Domergue, C., Philibert, H., Destouches, C., Thiollay, N., Girard, J.M.
Format: Conference Proceeding
Language:English
Subjects:
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:Reactor dosimetry is based on the analysis of the activity of irradiated dosimeters, such as $^{93m}$Nb and $^{103m}$Rh. The activity measurement of these dosimeters is conventionally performed by X-ray spectrometry, but the low-energy of emitted photons makes it difficult to derive reliable results with low uncertainties. Approaches to improve these characterisations are presented: they include high accuracy efficiency calibration of a HPGe detector using both experiments and Monte Carlo simulation, calculation of corrective factors for the geometry (selfabsorption) and self-fluorescence effects. Improvement of the knowledge of the $^{103m}$Rh decay scheme is also required and a specific experiment is proposed, including activity measurement of a $^{103m}$Rh solution by liquid scintillation, and measurement of the photon emission intensities by X-ray spectrometry. A method for calculating coefficients to take into account the self-fluorescence effects in dosimeters is also suggested to improve the uncertainties on activity measurements.
ISSN:2100-014X
DOI:10.1051/epjconf/201715307009