Easy-to-Use Online Software Package for Internal Dose Assessment After Radionuclide Treatment in Clinical Routine

2013 ◽  
Vol 38 (9) ◽  
pp. 686-690 ◽  
Author(s):  
Siroos Mirzaei ◽  
Antti Sohlberg ◽  
Peter Knoll ◽  
Rasoul Zakavi ◽  
Markus Diemling
Keyword(s):  
Software Package ◽  
Dose Assessment ◽  
Internal Dose ◽  
Clinical Routine ◽  
Online Software

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

2006 ◽  
Vol 34 (3) ◽  
pp. 413-421 ◽  
Author(s):  
Eric Visser ◽  
Ernst Postema ◽  
Otto Boerman ◽  
Jeroen Visschers ◽  
Wim Oyen ◽  
...  
Keyword(s):  
Nuclear Medicine ◽  
Data Processing ◽  
Software Package ◽  
Dose Assessment ◽  
Internal Dose

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

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.

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

2008 ◽  
Vol 99 (9) ◽  
pp. 1449-1455 ◽  
Author(s):  
J.M. Gómez-Ros ◽  
G. Pröhl ◽  
A. Ulanovsky ◽  
M. Lis
Keyword(s):  
Dose Assessment ◽  
Internal Dose

Internal Dose Assessment of New 177Lu-Radiopharmaceuticals and Its Role in Radiation Protection of Patients

2016 ◽  
Vol 173 (1-3) ◽  
pp. 192-197
Author(s):  
Nancy Puerta Yepes ◽  
Ana Rojo ◽  
Sebastián Gossio ◽  
José Luis Crudo
Keyword(s):  
Radiation Protection ◽  
Dose Assessment ◽  
Internal Dose

Automatic application of ICRP biokinetic models in voxel phantoms for in vivo counting and internal dose assessment

2007 ◽  
Vol 127 (1-4) ◽  
pp. 240-244 ◽  
Author(s):  
S. Lamart ◽  
L. de Carlan ◽  
E. Blanchardon ◽  
D. Franck
Keyword(s):  
Dose Assessment ◽  
Internal Dose ◽  
Voxel Phantoms

INTERCOMPARISON ON INTERNAL DOSE ASSESSMENT FOR NUCLEAR POWER PLANTS IN KOREA

2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Dose Assessment ◽  
Assessment Procedure ◽  
Internal Dose ◽  
Nuclear Facilities ◽  
International Intercomparison ◽  
Selection Of

Abstract The intercomparison test is a quality assurance activity performed for internal dose assessment. In Korea, the intercomparison test on internal dose assessment was carried out for nuclear facilities in May 2018. The test involved four nuclear facilities in Korea, and seven exposure scenarios were applied. These scenarios cover the intake of 131I, a uranium mixture, 60Co and tritium under various conditions. This paper only reviews the participant results of three scenarios pertinent to the operation of nuclear power plants and adopts the statistical evaluation method, used in international intercomparison tests, to determine the significance values of the results. Although no outliers were established in the test, improvements in the internal dose assessment procedure were derived. These included the selection of intake time, selection of lung absorption type according to the chemical form and consideration of the contribution of previous intake.

JADA: A graphical user interface for comprehensive internal dose assessment in nuclear medicine

2013 ◽  
Vol 40 (7) ◽  
pp. 072501 ◽  
Author(s):  
Joshua Grimes ◽  
Carlos Uribe ◽  
Anna Celler
Keyword(s):  
Nuclear Medicine ◽  
User Interface ◽  
Graphical User Interface ◽  
Dose Assessment ◽  
Internal Dose
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