scholarly journals Internal radiation dose assessment of radiopharmaceuticals prepared with cyclotron-produced99mTc

2019 ◽  
Vol 46 (3) ◽  
pp. 1437-1446 ◽  
Author(s):  
Laura Meléndez-Alafort ◽  
Guillermina Ferro-Flores ◽  
Laura De Nardo ◽  
Michele Bello ◽  
Marta Paiusco ◽  
...  
Keyword(s):  
Radiation Dose ◽  
Dose Assessment ◽  
Internal Radiation ◽  
Radiation Dose Assessment

scholarly journals Internal Radiation Dose Assessment using IRDA Software for Bangladeshi Subjects due to Ingestion of CO-60

2013 ◽  
Vol 4 (1) ◽  
pp. 135-143
Author(s):  
AHMR Quddus ◽  
M Moksed Ali ◽  
MMA Zaman ◽  
AS Mollah
Keyword(s):  
Radiation Dose ◽  
Age Groups ◽  
Absorbed Dose ◽  
Equivalent Dose ◽  
Dose Assessment ◽  
Gi Tract ◽  
Internal Radiation ◽  
Radiation Dose Assessment ◽  
Tissue Compartments ◽  
Committed Effective Dose

Retention, absorbed dose, committed equivalent dose and committed effective doses have been assessed due to acute ingestion of 1 Bq of 60Co in human body. Calculations are done using “Internal Radiation Dose Assessment (IRDA)” software which has been developed based on the biokinetic model. Due to ingestion maximum radiation dose is deposited in the gastro intestinal (GI) tract, assumed to consist of four tissue compartments, e.g. stomach (ST), small intestine (SI), upper large intestine (ULI) and lower large intestine (LLI). In this work actual tissue masses of GI Tract of Bangladeshi people have been considered to calculate the above mentioned quantities for different age groups, such as 1 yr, 10 yrs and adult (female and male). One hour after the ingestion, the retention and absorbed dose show the trend ST > SI > ULI > LLI. Regarding tissue compartments the variation of the committed equivalent dose pattern is LLI > ULI > ST > SI for the radionuclide. The variation of absorbed dose, committed equivalent dose and committed effective dose with respect to age follow the pattern: 1 yr > 10yrs > adult female > adult male. The highest committed effective dose for ingestion of 1 Bq of the radionuclide under the study is found in the GI tract of 1 yr old child. This value is 6.56 x 10-6 mSv. For other age groups these values are slightly less. DOI: http://dx.doi.org/10.3329/bjmp.v4i1.14703 Bangladesh Journal of Medical Physics Vol.4 No.1 2011 135-143

scholarly journals Uncertainty of fast biological radiation dose assessment for emergency response scenarios

2016 ◽  
Vol 93 (1) ◽  
pp. 127-135 ◽  
Author(s):  
Elizabeth A. Ainsbury ◽  
Manuel Higueras ◽  
Pedro Puig ◽  
Jochen Einbeck ◽  
Daniel Samaga ◽  
...  
Keyword(s):  
Radiation Dose ◽  
Emergency Response ◽  
Dose Assessment ◽  
Radiation Dose Assessment

Conceptus radiation dose assessment from fluoroscopically assisted surgical treatment of hip fractures

2003 ◽  
Vol 30 (10) ◽  
pp. 2594-2601 ◽  
Author(s):  
J. Damilakis ◽  
N. Theocharopoulos ◽  
K. Perisinakis ◽  
G. Papadokostakis ◽  
A. Hadjipavlou ◽  
...  
Keyword(s):  
Surgical Treatment ◽  
Radiation Dose ◽  
Hip Fractures ◽  
Dose Assessment ◽  
Radiation Dose Assessment

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

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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