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The pure alpha emitter  148 Gd may have a significant radiological impact in terms of internal dose to exposed humans in case of accidental releases from a spallation source using a tungsten target, such as the one to be used in the European Spallation Source (ESS). In this work we aim to present an approach to indirectly estimate the whole-body burden of  148 Gd and the associated committed effective dose in exposed humans, by means of high-resolution gamma spectrometry of the gamma-emitting radiogadolinium isotopes  146 Gd and  153 Gd that are accompanied by  148 Gd generated from the operation of the tungsten target. Theoretical minimum detectable whole-body activity (MDA) and associated internal doses from  148 Gd are calculated using a combination of existing biokinetic models and recent computer simulation studies on the generated isotope ratios of  146 Gd/ 148 Gd and  153 Gd/ 148 Gd in the ESS target. Of the two gamma-emitting gadolinium isotopes,  146 Gd is initially the most sensitive indicator of the presence of  148 Gd if whole-body counting is performed within a month after the release, using the twin photo peaks of  146 Gd centered at 115.4 keV (MDA < 1 Bq for ingested  148 Gd, and < 25 Bq for inhaled  148 Gd). The corresponding minimum detectable committed effective doses will be less than 1 µSv for ingested  148 Gd, but substantially higher for inhaled  148 Gd (up to 0.3 mSv), depending on operation time of the target prior to the release. However, a few months after an atmospheric release,  153 Gd becomes a much more sensitive indicator of body burdens of  148 Gd, with a minimum detectable committed effective doses ranging from 18 to 77 µSv for chronic ingestion and between 0.65 to 2.7 mSv for acute inhalation in connection to the release. The main issue with this indirect method for  148 Gd internal dose estimation, is whether the primary photon peaks from  146  and  153 Gd can be detected undisturbed. Preliminary simulations show that nuclides such as  182 Ta may potentially create perturbations that could impair this evaluation method, and which impact needs to be further studied in future safety assessments of accidental target releases.

Internal dose assessment of 148Gd using isotope ratios of gamma-emitting 146Gd or 153Gd in accidently released spallation target particles