Radiation dose to patients from radiopharmaceuticals: (Addendum 2 to ICRP Publication 53) ICRP Publication 80 Approved by the Commission in September 1997

1998 ◽  
Vol 28 (3) ◽  
pp. 1-1 ◽  
Author(s):  
J. Valentin
Keyword(s):  
Carbon Dioxide ◽  
Fatty Acids ◽  
Radiation Dose ◽  
Unit Activity ◽  
The Public ◽  
Absorbed Doses ◽  
Joint Task ◽  
Age Dependent ◽  
Effective Doses ◽  
Icrp Publication

A joint Task Group of ICRP Committees 2 (Doses from Radiation Exposures) and 3 (Protection in Medicine; lead Committee for this report) has prepared a compilation of data on radiation dose to patients from radiopharmaceuticals. The report provides biokinetic models, absorbed doses, and effective doses, using ICRP Publication 60 dosimetry, for 10 new radiopharmaceuticals: [Methyl-11C]thymidine; [2-11C]thymidine; 14C urea (incl. carbon dioxide and bicarbonate); 15O water; 99mTc HIG, Pertechnegas, Technegas, and tetrofosmin; and 111In HIG and octreotide. It also provides recalculated dose data for the 19 most frequently used radiopharmaceuticals from ICRP Publication 53, using ICRP Publication 60 dosimetry, viz. 18F FDG; 51Cr EDTA; 67Ga citrate; 75Se SeHCAT; 99mTc DMSA, DTPA, RBC, IDA, large colloids, WBC, MAA, non-absorbable markers, pertechnetate, and phosphates and phosphonates; 123I Hippuran and MIBG; 131I Hippuran and NP59; and 201Tl thallous ion. Printing errors detected in ICRP Publication 53 are also listed. Furthermore, the report reproduces with minor corrections and updates, and therefore supersedes, the information on 6 radiopharmaceuticals given in Addendum 1 to ICRP Publication 53: 3H neutral fat and fatty acids; 14C neutral fat and fatty acids; 68Ga EDTA; and 99mTc HM-PAO, MAG3, and MIBI. There is an integrated index to all radiopharmaceuticals treated in ICRP publications so far, including a listing of effective doses per unit activity administered to adults. This issue of the Annals of the ICRP also includes an Addendum to ICRP Publication 72 concerning age-dependent doses to members of the public from intakes of radionuclides.

Radiation absorbed dose estimates for 18F-BPA PET

2017 ◽  
Vol 58 (9) ◽  
pp. 1094-1100 ◽  
Author(s):  
Yuzuru Kono ◽  
Hiroaki Kurihara ◽  
Hiroshi Kawamoto ◽  
Naoko Yasui ◽  
Naoki Honda ◽  
...  
Keyword(s):  
Cancer Cells ◽  
Pediatric Patients ◽  
The Body ◽  
Adult Patients ◽  
Absorbed Doses ◽  
Pet Tracer ◽  
Effective Doses ◽  
18F Fdg ◽  
Age Range ◽  
Icrp Publication

Background Boron neutron capture therapy (BNCT) is a molecular radiation therapy approach based on the 10B (n, α) 7Li nuclear reaction in cancer cells. In BNCT, delivery of 10B in the form of 4-borono-phenylalanine conjugated with fructose (BPA-fr) to the cancer cells is important. The PET tracer 4-borono-2-18F-fluoro-phenylalanine (FBPA) has been used to predict the accumulation of BPA-fr before BNCT. Purpose To determine the biodistribution and dosimetric parameters in 18F-BPA PET/CT studies. Material and Methods Human biokinetic data were obtained during clinical 18F-BPA PET studies between February and June 2015 at one institution. Nine consecutive patients were studied prospectively. The internal radiation dose was calculated on the basis of radioactivity data from blood, urine, and normal tissue of the heart, liver, spleen, kidney, and other parts of the body at each time point using OLINDA/EXM1.1 program. We compared our calculations with published 18F-FDG data. Results Adult patients (3 men, 3 women; age range, 28–68 years) had significantly smaller absorbed doses than pediatric patients (3 patients; age range, 5–12 years) ( P = 0.003). The mean effective dose was 57% lower in adult patients compared with pediatric patients. Mean effective doses for 18F-BPA were 25% lower than those for 18F-FDG presented in International Commission of Radiation Protection (ICRP) publication 106. Conclusion We found significant differences in organ absorbed doses for 18F-BPA against those for 18F-FDG presented in ICRP publication 106. Mean effective doses for 18F-BPA were smaller than those for 18F-FDG in the publication by 0.5–38% (mean difference, 25%).

scholarly journals Radiation-hygienic monitoring and assessment of the doses of the public residing on the radioactively contaminated territories of the Tula region

2019 ◽  
Vol 12 (2(св)) ◽  
pp. 115-120
Author(s):  
A. E. Lomovtsev ◽  
T. E. Sheveleva ◽  
A. S. Karpukhin ◽  
A. I. Volodicheva
Keyword(s):  
Radiation Dose ◽  
Annual Effective Dose ◽  
Food Products ◽  
Radiation Dose Rate ◽  
The Public ◽  
Collective Dose ◽  
Chernobyl Npp ◽  
Effective Doses ◽  
Medical Exposure ◽  
Gamma Radiation Dose

Aim of the study: analysis of the results of the radiation-hygienic monitoring of the territories of the Tula region, contaminated due to the Chernobyl NPP accident; concentration of 137Cs and 90Sr in the locally produced food products and analysis of the annual effective dose of the public. Materials and methods: the study was performed in the Tula region in 1997-2018. It included the evaluation of the indicators of the radiation safety of more than 50 thousand samples of the main food products, sampled in the areas of the radioactive “Chernobyl” contamination of the region with the simultaneous measurement of the external gamma-radiation dose rate in the stationary control points. Additionally, it included the assessment of the dynamics of concentration of 137Cs and 90Sr in food products, maximal values of mean annual effective doses of the public and contribution of the collective dose from medical exposure into the structure of the annual collective dose of the public. Results: The study allowed estimating the concentration of 137Cs and 90Sr in the main local food products. Estimated values of gamma radiation dose rate were stable and laid in the range of normal variations specific to the middle latitudes of the European part of Russia. The values of maximal mean annual effective doses of the public indicate the stable radiation environment and do not exceed 1 mSv. It should be mentioned that the contribution of collective dose from medical exposure into the annual collective dose of the public as well as the values of mean individual effective doses from medical exposure are reducing with the increase in the number of X-ray examinations. Conclusions: The lack of exceedances of the permissible levels of 137Cs and 90Sr in the locally produced food products and the reduction of the mean annual effective dose of the public indicates the possibility of the transfer of the settlements affected by the Chernobyl NPP accident into the normal living conditions within the program of the transfer of the settlements from the “Chernobyl” zone.

Reconstructive dosimetry and radiation dose evaluation of workers and public due to a brazilian radiological accident in industrial radiography

2021 ◽  
Author(s):  
Camila Moreira Araujo de Lima ◽  
Tadeu Augusto de Almeida Silva ◽  
John Graham Hunt ◽  
Francisco Cesar Augusto Da Silva
Keyword(s):  
Radiation Dose ◽  
Absorbed Dose ◽  
Dose Calculation ◽  
Radioactive Source ◽  
Nuclear Accidents ◽  
The Public ◽  
Industrial Radiography ◽  
Parking Lot ◽  
Radiation Workers ◽  
Effective Doses

Abstract Radiological accidents occur mainly in the practices recognized as high risk and which are classified by the IAEA as Categories 1 and 2: radiotherapy, industrial irradiators and industrial radiography. In Brazil, 5 important cases in industrial gamma radiography occurred from 1985 to 2018, involving 7 radiation workers and 19 members of the public. The accidents caused localized radiation lesions on the hands and fingers. One of these accidents is the focus of this paper. In this accident, a 3.28 TBq 192Ir radioactive source was left unshielded for 9 hours in a NDT company parking lot, and many radiation workers, employees and public, including teachers of a primary school were exposed. The radioactive source was also directly handled by a security worker for about 1.5 min causing severe radiation injuries in the hand and fingers. This paper presents radiation dose estimates for all accidentally exposed individuals. Four scenarios were considered, and three internationally recognised and updated reconstructive dosimetry techniques were used, named, Brazilian Visual Monte Carlo Dose Calculation (VMC), Virtual Environment for Radiological and Nuclear Accidents Simulation (AVSAR) and RADPRO Calculator®. The main radiation doses estimated by VMC were the absorbed dose of 34 Gy for the security worker’s finger and his effective dose of 91 mSv; effective doses from 43 to 160 mSv for radiation workers and NDT employees; and effective doses of 9 mSv for teachers in the schoolyard.

7. Inhalation dose coefficients for members of the public: labelled methane: (Addendum 1 to ICRP Publication 72)

1998 ◽  
Vol 28 (3) ◽  
pp. 123-123
Author(s):  
D. J. Valentin
Keyword(s):  
Inhalation Dose ◽  
The Public ◽  
Task Groups ◽  
Age Dependent ◽  
Dose Coefficients ◽  
Icrp Publication

This is an Addendum to ICRP Publication 72 concerning age-dependent doses to members of the public from intakes of radionuclides. It provides inhalation dose coefficients for labelled methane for members of the public, jointly prepared by two Task Groups of ICRP Committee 2.

scholarly journals Radiation Dose Calculations for a Hypothetical Accident in Xianning Nuclear Power Plant

2016 ◽  
Vol 2016 ◽  
pp. 1-6 ◽  
Author(s):  
Bo Cao ◽  
Junxiao Zheng ◽  
Yixue Chen
Keyword(s):  
Radiation Dose ◽  
Nuclear Power ◽  
Atmospheric Dispersion ◽  
Harmful Effect ◽  
Atmospheric Stability ◽  
Dispersion Modeling ◽  
Dose Calculations ◽  
Air Concentration ◽  
The Public ◽  
Ground Deposition

Atmospheric dispersion modeling and radiation dose calculations have been performed for a hypothetical AP1000 SGTR accident by HotSpot code 3.03. TEDE, the respiratory time-integrated air concentration, and the ground deposition are calculated for various atmospheric stability classes, Pasquill stability categories A–F with site-specific averaged meteorological conditions. The results indicate that the maximum plume centerline ground deposition value of1.2E+2 kBq/m2occurred at about 1.4 km and the maximum TEDE value of1.41E-05 Sv occurred at 1.4 km from the reactor. It is still far below the annual regulatory limits of 1 mSv for the public as set in IAEA Safety Report Series number 115. The released radionuclides might be transported to long distances but will not have any harmful effect on the public.

PRELIMINARY EVALUATION OF PATIENT RADIATION DOSES DURING RADIONUCLIDE DIAGNOSTIC WITH MONOCLONAL ANTIBODIES LABELED WITH 89Zr

2021 ◽  
Author(s):  
Larisa A. Chipiga ◽  
Anna E. Petrova ◽  
Artem A. Mosunov ◽  
Laura T. Naurzbaeva ◽  
Stanislaus M. Kushnarenko ◽  
...  
Keyword(s):  
Monoclonal Antibodies ◽  
Dose Assessment ◽  
Published Data ◽  
Radiation Doses ◽  
Preliminary Evaluation ◽  
Software Products ◽  
Absorbed Doses ◽  
Order Of Magnitude ◽  
Effective Doses

In connection with the constantly increasing use of monoclonal antibodies labeled with 89Zr, in clinical practice, it is urgent to study their pharmacokinetics with the determination, based on the data obtained, of absorbed doses in tumor foci, as well as intact organs and tissues, and effective doses of patients. To date, there are a limited number of studies that provide patient doses for diagnostic examinations using 89Zr-labeled monoclonal antibodies. In this regard, the purpose of this work was to assess the biodistribution of various monoclonal antibodies (ramucirumab, trastuzumab, atezolizumab) labeled with 89Zr, based on published data, with subsequent calculation of absorbed doses in radiosensitive organs and tissues and effective doses of patients. Based on the analysis of experimental data on the biodistribution of monoclonal antibodies labeled with 89Zr for the diagnosis of oncological diseases from the available literature sources and our own assessments, it has been concluded that the results of the determination of absorbed in organs and tissues and effective doses are inconsistent. The absorbed doses in organs, according to different literature sources, vary up to an order of magnitude within one organ and reach 440 mGy per examination, the effective dose varies from 3 to 112 mSv per examination. This may be due to differences in study design, radiometry and dose assessment methods. Comparison with doses obtained on the basis of a general model of biodistribution of monoclonal antibodies demonstrates the possibility of using this model for a rough estimate of internal doses of patients. However, for a more accurate assessment, it is necessary to standardize approaches to the determination of internal radiation doses using the most effective methodological solutions and software products.

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