Software package for integrated data processing for internal dose assessment in nuclear medicine (SPRIND)

At about 70% of nuclear medicine procedures have utilized 99mTc in their clinical practices.This has lead 99mTc becoming the most convenient radioisotope in nuclear medicine diagnostic. To estimate the internal radiation dose due to the administration of 99mTc to the patients, only few documents from International Commission of Radiation Protection (ICRP) have been available. However, the calculation usually has applied Caucasian data in Standard Reference Man as a model. The objective of this study was to review the application of 99mTc in Indonesia and to compare the internal dose estimation for 99mTc procedures by using Organ Level Internal Dose Assessment/ EXponential Modeling (OLINDA/EXM) software. The result of calculation was compared between Adult Caucasian model and Asian Reference Man. The result shows that 99mTc has been well applied and developed for diagnostic procedures in Nuclear Medicine Department. Moreover, in most diagnostic procedures using 99mTc in Indonesia, adult patients will receive effective dose about 1-15% higher than adult patient in foreign countries which apply the Caucasian model. Hence, to estimate the similar stochastic risk from the same procedure, the maximum value in recommended administered dose should be avoided and need to be evaluated.

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

Scientific Reports ◽

10.1038/s41598-020-77718-3 ◽

2020 ◽

Vol 10 (1) ◽

Author(s):

C. Rääf ◽

V. Barkauskas ◽

K. Eriksson Stenström ◽

C. Bernhardsson ◽

H. B. L. Pettersson

Keyword(s):

Operation Time ◽

Isotope Ratios ◽

Dose Assessment ◽

Sensitive Indicator ◽

Whole Body ◽

Internal Dose ◽

Tungsten Target ◽

Alpha Emitter ◽

Spallation Source ◽

Effective Doses

AbstractThe pure alpha emitter 148Gd 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 148Gd and the associated committed effective dose in exposed humans, by means of high-resolution gamma spectrometry of the gamma-emitting radiogadolinium isotopes 146Gd and 153Gd that are accompanied by 148Gd generated from the operation of the tungsten target. Theoretical minimum detectable whole-body activity (MDA) and associated internal doses from 148Gd are calculated using a combination of existing biokinetic models and recent computer simulation studies on the generated isotope ratios of 146Gd/148Gd and 153Gd/148Gd in the ESS target. Of the two gamma-emitting gadolinium isotopes, 146Gd is initially the most sensitive indicator of the presence of 148Gd if whole-body counting is performed within a month after the release, using the twin photo peaks of 146Gd centered at 115.4 keV (MDA < 1 Bq for ingested 148Gd, and < 25 Bq for inhaled 148Gd). The corresponding minimum detectable committed effective doses will be less than 1 µSv for ingested 148Gd, but substantially higher for inhaled 148Gd (up to 0.3 mSv), depending on operation time of the target prior to the release. However, a few months after an atmospheric release, 153Gd becomes a much more sensitive indicator of body burdens of 148Gd, 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 148Gd internal dose estimation, is whether the primary photon peaks from 146 and 153Gd can be detected undisturbed. Preliminary simulations show that nuclides such as 182Ta 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.

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Data processing in nuclear medicine

2014 20th International Workshop on Beam Dynamics and Optimization (BDO) ◽

10.1109/bdo.2014.6890037 ◽

2014 ◽

Cited By ~ 2

Author(s):

Elena D. Kotina ◽

Dmitri A. Ovsyannikov ◽

Victor A. Ploskikh ◽

Victor N. Latipov ◽

Andrey V. Babin ◽

...

Keyword(s):

Nuclear Medicine ◽

Data Processing

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Nuclear Medicine Physics, Instrumentation, and Data Processing in Pharmaceutical Research

Nuclear Imaging in Drug Discovery, Development, and Approval ◽

10.1007/978-1-4684-6808-3_2 ◽

1993 ◽

pp. 11-31

Author(s):

Jonathan M. Links

Keyword(s):

Nuclear Medicine ◽

Data Processing ◽

Pharmaceutical Research

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Uncertainties of internal dose assessment for animals and plants due to non-homogeneously distributed radionuclides

Journal of Environmental Radioactivity ◽

10.1016/j.jenvrad.2008.01.005 ◽

2008 ◽

Vol 99 (9) ◽

pp. 1449-1455 ◽

Cited By ~ 27

Author(s):

J.M. Gómez-Ros ◽

G. Pröhl ◽

A. Ulanovsky ◽

M. Lis

Keyword(s):

Dose Assessment ◽

Internal Dose

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Patient radiation dose assessment system for diagnostic nuclear medicine procedures: Implementation and first results

Nuclear Technology and Radiation Protection ◽

10.2298/ntrp2004380d ◽

2020 ◽

Vol 35 (4) ◽

pp. 380-385

Author(s):

Dea Dundara-Debeljuh ◽

Slaven Jurkovic ◽

Ivan Pribanic ◽

Neva Girotto ◽

Svjetlana Grbac-Ivankovic ◽

...

Keyword(s):

Nuclear Medicine ◽

Radiation Dose ◽

Radiation Risk ◽

Assessment System ◽

Dose Assessment ◽

Medical Documentation ◽

Diagnostic Nuclear Medicine ◽

Nuclear Medicine Procedures ◽

Radiation Dose Assessment ◽

Patient Radiation Dose

Dose assessment of diagnostic nuclear medicine procedures is necessary to further optimize respective procedure, estimate radiation risk, improve radiation safety and verify compliance of local practice with guidelines. In line with Council Directive 2013/59/EURATOM, patient medical documentation should include information related to radiation exposure. The aim of this work is to present the patient radiation dose assessment system designed for routine clinical use, that uses in-house designed worksheets for dose calculation based on relevant parameters introduced by the ICRP publications. Dose reports provide information about the absorbed dose delivered to the target and non-target organs of interest and the effective dose for each diagnostic procedure. The data from the dose reports was used to investigate average patient exposure levels during a one-year period and the results are presented. The implemented system has improved the quality of services provided and understanding of radiation risks. Moreover, the presented results have stimulated further optimization of nuclear medicine processes.

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