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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...
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Main Authors: | , , , , , , |
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Format: | Conference Proceeding |
Language: | English |
Subjects: | |
Online Access: | Get full text |
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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. |
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ISSN: | 2100-014X |
DOI: | 10.1051/epjconf/201715307009 |