scholarly journals A Computer Program for Calculation of Approximate Embryo/Fetus Radiation Dose in Nuclear Medicine Applications

2012 ◽  
Vol 21 (1) ◽  
pp. 19-22
Author(s):  
... ...
PEDIATRICS ◽  
1982 ◽  
Vol 70 (2) ◽  
pp. 231-234
Author(s):  
W. B. Pittard ◽  
R. Merkatz ◽  
B. D. Fletcher

Albumin-tagged sodium pertechnetate (technetium) is routinely used in nuclear medicine for scanning procedures of the lung. The rate of excretion of this radionuclide into breast milk and the resultant potential radiation hazard to the nursing infant have received little attention. Therefore the milk from a nursing mother who required a lung scan because of suspected pulmonary emboli using an intravenous injection of 4 mCi of technetium Tc 99 macroaggregated human serum albumin was monitored. Albumin tagging severely limited the entrance of technetium into her milk and the radio-activity of the milk returned to base line by 24 hours. A total of 2.02 µCi of technetium was measured in the 24-hour milk collection after technetium injection and 94% of this amount was excreted by 15.5 hours. This amount of technetium administered orally to a newborn would deliver a total body radiation dose of .3 mrad. Therefore, an infant would receive trivial doses of radiation if breast-feeding were resumed 15.5 hours after administration of the radionuclide to the mother and nursing can clearly be resumed safely 24 hours after injection.


2002 ◽  
Vol 45 (spe) ◽  
pp. 115-118
Author(s):  
Nicole Colas-Linhart

In nuclear medicine, radiation absorbed dose estimates calculated by standard models at the whole body or organ are very low. At cellular level, however, the heterogeneity of radionuclide distributions of radiation dose patterns may be significant. We present here absorbed doses at cellular level and evaluate their possible impact on the usually assumed risk/benefit relationships in nuclear medicine studies. The absorbed dose values calculated are surprisingly high, and are difficult to interpret. In the present study, we show calculated doses at the cellular level and discuss possible biological consequences, for two radiopharmaceuticals labelled with technetium-99m: human serum albumin microspheres used for pulmonary scintigrapies and HMPAO used to labelled leukocytes.


2020 ◽  
Vol 35 (4) ◽  
pp. 380-385
Author(s):  
Dea Dundara-Debeljuh ◽  
Slaven Jurkovic ◽  
Ivan Pribanic ◽  
Neva Girotto ◽  
Svjetlana Grbac-Ivankovic ◽  
...  

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.


Radiopraxis ◽  
2018 ◽  
Vol 11 (04) ◽  
pp. E30-E40
Author(s):  
Heribert Hänscheid ◽  
Frederik A. Verburg

Bei der Behandlung benigner Schilddrüsenerkrankungen mit 131I ist eine prätherapeutische Dosimetrie zur Bemessung der Therapieaktivität und eine Abschätzung der therapeutisch verabreichten Energiedosis in Deutschland gesetzlich vorgeschrieben. Zur Durchführung der Dosimetrie existieren Handlungsempfehlungen der Deutschen Gesellschaft für Nuklearmedizin und der European Association of Nuclear Medicine. Um Methodik und Verfahrensablauf der Dosisbestimmungen national weiter zu harmonisieren, wird aktuell die Norm DIN 6861 – 1 erstellt. Die DIN 6861 – 1 übernimmt viele Empfehlungen der Leitlinien als Forderungen und führt bei den Berechnungen zu vergleichbaren Ergebnissen. Im Detail finden sich aber auch Unterschiede, z. B. wird bei den Berechnungen die Abhängigkeit der absorbierten Energiedosis von der Größe des therapierten Volumens explizit berücksichtigt. Beim Formalismus verlässt die DIN 6861 – 1 die tradierten Schreibweisen und verwendet die international zunehmend als Standard für die Dosimetrie bei innerer Exposition akzeptierte Nomenklatur des Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine. Dem Nutzer wird durch die neue DIN-Norm zudem eine vollständige Liste der für eine nachvollziehbare Dosimetrie notwendigen Dokumentation an die Hand gegeben.


1977 ◽  
Vol 4 (2) ◽  
pp. 152
Author(s):  
P.F. Butler ◽  
L.T. Fitzgerald ◽  
K.N. Vanek ◽  
V.A. Brookeman

1996 ◽  
Vol 21 (2) ◽  
pp. 174
Author(s):  
Shashadhar M. Mohapatra ◽  
Larry D. Morefield ◽  
E. William Allen

2014 ◽  
Vol 44 (3) ◽  
pp. 202-209 ◽  
Author(s):  
S. Ted Treves ◽  
Anthony E. Falone ◽  
Frederic H. Fahey

1999 ◽  
Vol 20 (4) ◽  
pp. 396
Author(s):  
S. A. White ◽  
D. S. Binns ◽  
V. K. Johnston ◽  
M. F. Fawcett ◽  
B. Greer ◽  
...  

2003 ◽  
Vol 18 (1) ◽  
pp. 109-115 ◽  
Author(s):  
Isabelle Gardin ◽  
Lionel G. Bouchet ◽  
Karine Assié ◽  
Jerome Caron ◽  
Albert Lisbona ◽  
...  

2019 ◽  
Vol 30 (1) ◽  
pp. 65-78
Author(s):  
Abdulmalek Rajkhan Abdulmalek Rajkhan

Radiation induced cataracts is a disease that is common amongst radiation exposed staff. About 30 percent of retired occupational radiation workers developed eye lens (EL) cataracts. Epidemiological studies on radiation therapy patients, occupational workers, and atomic bomb survivors show that 0.5 Gy of acute or fractioned radiation dose to EL causes one or both lens to cloud. The annual EL dose limit drawn by the International Commission for Radiation Protection (ICRP) was 150 mSv and was changed in 2012 to 20 mSv averaged over 5 years, with no single year exceeding 50 mSv. The limited number of researche done in Nuclear Medicine (NM) clinics with the Hp(3) dosimeters suggest that the annual EL dose from three procedures is measured to be between 4.5 and 9 mSv (i.e. dispensing, preparing and administering). These procedures are performed when the radioactive materials are in closed shielded containers or behind a barrier. Common radioactive material handled by occupational workers in NM clinics are 99mTc and 131I. They pose less radiation hazard to workers EL in the three procedures when they are behind shielded containers. Moreover, once the radioactive material is administered into patients, they become open sources and pose more radiation hazard to workers. The Hp(3) dosimeter is a new uncommon dosimeter. Many radiation facilities use the Hp(0.07) and Hp(10) dosimeters coupled with many conditions and conversion factors to find approximate results. Therefore, simulations are performed to find the EL dose. However, some simulations are performed with little flexibility in simulation geometry, others utilize low-quality phantoms or present the simulation results in terms of fluxes or energy ranges. In the present study, the NM worker EL dose is simulated by utilizing a high-resolution Digital Imagning Communication in Medicine (DICOM) image in GEANT4 Archeticture for Medical Oriented Simulation (GAMOS). A water cylinder homogenously filled by radioactive material, representing the administered patient, was created in the simulation. The worker exposure scenario was simulated by placing the cylinder in three different directions and five different distances with respect to the DICOM image. The results of the simulation reveal that the highest occupational EL radiation dose is received from the anterior-posterior direction, followed by the lateral, and the posterior-anterior directions. The results of the conservative simulated scenario reveal that the worker EL dose is exposed to three tenths of the annual dose limit after 110 131I patients, or 300 99mTc patients.


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