scholarly journals Model for calculating energy absorption in environmental objects from incorporated sources of monoenergetic electrons

2021 ◽  
Vol 30 (2) ◽  
pp. 113-122
Author(s):  
T.G. Sazykina ◽  
◽  
A.I. Kryshev ◽  
Keyword(s):  
Energy Absorption ◽  
Data Model ◽  
Radiation Dosimetry ◽  
Internal Radiation ◽  
Environmental Radiation ◽  
Biological Objects ◽  
Environmental Objects ◽  
Testing Data ◽  
Model Equations ◽  
Fitting Parameters

Model is suggested to calculating energy absorption in organisms of various geometry from in-corporated sources of monoenergetic electrons. The effectiveness of the approach was demon-strated for spheres, ellipsoids, and cylinders by comparison of analytical values with large inter-national testing data. Model equations are free of any fitting parameters; computer approximating procedures are not employed. The method allows to make correct express-calculations of inter-nal absorbed doses in various biological objects from beta emitting radionuclides; the calcula-tions are performed without Monte Carlo codes. The model may be used in the internal radiation dosimetry for non-human biota, and in environmental radiation protection.

scholarly journals Biodistribution and internal radiation dosimetry of a companion diagnostic radiopharmaceutical, [68Ga]PSMA-11, in subcutaneous prostate cancer xenograft model mice

2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Su Bin Kim ◽  
In Ho Song ◽  
Yoo Sung Song ◽  
Byung Chul Lee ◽  
Arun Gupta ◽  
...  
Keyword(s):  
Prostate Cancer ◽  
Radiation Dosimetry ◽  
Xenograft Model ◽  
Absorbed Dose ◽  
Patient Specific ◽  
Internal Radiation ◽  
Washout Phase ◽  
Heterogeneous Tissue ◽  
Organ Level ◽  
Reported Data

Abstract[68Ga]PSMA-11 is a prostate-specific membrane antigen (PSMA)-targeting radiopharmaceutical for diagnostic PET imaging. Its application can be extended to targeted radionuclide therapy (TRT). In this study, we characterize the biodistribution and pharmacokinetics of [68Ga]PSMA-11 in PSMA-positive and negative (22Rv1 and PC3, respectively) tumor-bearing mice and subsequently estimated its internal radiation dosimetry via voxel-level dosimetry using a dedicated Monte Carlo simulation to evaluate the absorbed dose in the tumor directly. Consequently, this approach overcomes the drawbacks of the conventional organ-level (or phantom-based) method. The kidneys and urinary bladder both showed substantial accumulation of [68Ga]PSMA-11 without exhibiting a washout phase during the study. For the tumor, a peak concentration of 4.5 ± 0.7 %ID/g occurred 90 min after [68Ga]PSMA-11 injection. The voxel- and organ-level methods both determined that the highest absorbed dose occurred in the kidneys (0.209 ± 0.005 Gy/MBq and 0.492 ± 0.059 Gy/MBq, respectively). Using voxel-level dosimetry, the absorbed dose in the tumor was estimated as 0.024 ± 0.003 Gy/MBq. The biodistribution and pharmacokinetics of [68Ga]PSMA-11 in various organs of subcutaneous prostate cancer xenograft model mice were consistent with reported data for prostate cancer patients. Therefore, our data supports the use of voxel-level dosimetry in TRT to deliver personalized dosimetry considering patient-specific heterogeneous tissue compositions and activity distributions.

Uniform-Panel Weld Shrinkage Data Model for Neat Construction Ship Design Engineering

2013 ◽  
Vol 29 (01) ◽  
pp. 1-16
Author(s):  
Yu-Ping Yang ◽  
Harvey Castner ◽  
Randy Dull ◽  
James R. Dydo ◽  
Dennis Fanguy
Keyword(s):  
Prediction Model ◽  
Data Model ◽  
Arc Welding ◽  
Gas Metal Arc Welding ◽  
Ease Of Use ◽  
Design Engineering ◽  
Microsoft Excel ◽  
Metal Arc Welding ◽  
Model Equations ◽  
Submerged Arc

A weld shrinkage prediction model was developed for thin uniform ship panels to predict in-plane shrinkage. The weld shrinkage prediction model consists of a series of empirical equations developed by analysis of shrinkage data from welded panels fabricated in the shipyards. These panels ranged in thickness from 3 mm to 9.5 mm and were welded with processes including submerged arc, flux cored arc, and gas metal arc welding. All fabrication data were carefully recorded using practices that were common over each of the shipyards. Measurements of the panels were made throughout each step of fabrication to provide accurate weld shrinkage data. The data were then analyzed by regression analysis to produce equations that permit the calculation of weld shrinkage based on the conditions used for fabrication. These shrinkage model equations were embedded in a Microsoft Excel spreadsheet for ease of use.

scholarly journals Internal Radiation Dosimetry: Models and Applications

10.5772/25363 ◽  
2011 ◽  
Author(s):  
Ernesto Amato ◽  
Alfredo Campenni ◽  
Astrid Herberg ◽  
Fabio Minutoli ◽  
Sergio Baldari
Keyword(s):  
Radiation Dosimetry ◽  
Internal Radiation

scholarly journals Internal radiation dosimetry of a 152Tb-labeled antibody in tumor-bearing mice

2019 ◽  
Vol 9 (1) ◽  
Author(s):  
Francesco Cicone ◽  
Silvano Gnesin ◽  
Thibaut Denoël ◽  
Thierry Stora ◽  
Nicholas P. van der Meulen ◽  
...  
Keyword(s):  
Radiation Dosimetry ◽  
Internal Radiation ◽  
Tumor Bearing

A comparison between GATE4 results and MCNP4B published data for internal radiation dosimetry

2011 ◽  
Vol 50 (03) ◽  
pp. 122-133 ◽  
Author(s):  
A. A. Parach ◽  
H. Rajabi
Keyword(s):  
Nuclear Medicine ◽  
Radiation Dosimetry ◽  
Published Data ◽  
Internal Dosimetry ◽  
Internal Dose ◽  
Internal Radiation ◽  
Cross Absorption ◽  
The Difference ◽  
Male Activity ◽  
Voxel Phantoms

SummaryAim: GATE, has been designed as upper layer of the GEANT4 toolkit for nuclear medicine application including internal dosimetry. However, its results have not been fully compared to the well-developed codes and anthropomorphic voxel phantoms have never been used with GATE/GEANT for internal dosimetry. The aim of present study was to compare the internal dose calculated by GATE/GEANT with the MCNP4B published data. Methods: The Zubal phantom was used to model a typical adult male. Activity was assumed uniformly distributed in liver, kidneys, lungs, spleen, pancreas and adrenals. GATE/ GEANT Monte Carlo package was used for estimation of doses in the phantom. Simulations were performed for photon energy of 0.01–1 MeV and mono-energetic electrons of 935 keV. Specific absorbed fractions for photons and S-factors for electrons were calculated. Results: On average, GATE/GEANT produces higher photon SAF (Specific Absorbed Fraction) values (+2.7%) for self-absorption and lower values (-2.9%) for cross-absorption. The difference was higher for paired organs particularly lungs. Moreover the photon SAF values for lungs as source organ at the energy of 200 and 500 keV was considerably higher with MCNP4B compared to GATE. Conclusion: Despite of differences between the GATE4 and MCNP4B, the results can be considered ensuring. This may be considered as validation of GATE/GEANT as a proprietary code in nuclear medicine for radionuclide dosimetry applications.

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