A biokinetic model for systemic sodium

2021 ◽  
Author(s):  
Caleigh Samuels ◽  
Rich Leggett
Keyword(s):  
Biokinetic Model

scholarly journals Radiopharmacokinetic modelling and radiation dose assessment of 223Ra used for treatment of metastatic castration-resistant prostate cancer

2021 ◽  
Vol 8 (1) ◽  
Author(s):  
Vera Höllriegl ◽  
Nina Petoussi-Henss ◽  
Kerstin Hürkamp ◽  
Juan Camilo Ocampo Ramos ◽  
Wei Bo Li
Keyword(s):  
Prostate Cancer ◽  
Radiological Protection ◽  
Bolus Administration ◽  
Time Activity ◽  
Biokinetic Model ◽  
Castration Resistant ◽  
Absorbed Doses ◽  
Red Marrow ◽  
Dose Coefficients ◽  
Modelling Study

Abstract Purpose Ra-223 dichloride (223Ra, Xofigo®) is used for treatment of patients suffering from castration-resistant metastatic prostate cancer. The objective of this work was to apply the most recent biokinetic model for radium and its progeny to show their radiopharmacokinetic behaviour. Organ absorbed doses after intravenous injection of 223Ra were estimated and compared to clinical data and data of an earlier modelling study. Methods The most recent systemic biokinetic model of 223Ra and its progeny, developed by the International Commission on Radiological Protection (ICRP), as well as the ICRP human alimentary tract model were applied for the radiopharmacokinetic modelling of Xofigo® biodistribution in patients after bolus administration. Independent kinetics were assumed for the progeny of 223Ra. The time activity curves for 223Ra were modelled and the time integrated activity coefficients, $$ \overset{\sim }{a}\left({r}_S,{T}_D\right), $$ a ~ r S T D , in the source regions for each progeny were determined. For estimating the organ absorbed doses, the Specific Absorbed Fractions (SAF) and dosimetric framework of ICRP were used together with the aforementioned $$ \overset{\sim }{a}\left({r}_S,{T}_D\right) $$ a ~ r S T D values. Results The distribution of 223Ra after injection showed a rapid plasma clearance and a low urinary excretion. Main elimination was via faeces. Bone retention was found to be about 30% at 4 h post-injection. Similar tendencies were observed in clinical trials of other authors. The highest absorbed dose coefficients were found for bone endosteum, liver and red marrow, followed by kidneys and colon. Conclusion The biokinetic modelling of 223Ra and its progeny may help to predict their distributions in patients after administration of Xofigo®. The organ dose coefficients of this work showed some variation to the values reported from clinical studies and an earlier compartmental modelling study. The dose to the bone endosteum was found to be lower by a factor of ca. 3 than previously estimated.

Simulations of reactive settling of activated sludge with a reduced biokinetic model

2016 ◽  
Vol 92 ◽  
pp. 216-229 ◽  
Author(s):  
Raimund Bürger ◽  
Julio Careaga ◽  
Stefan Diehl ◽  
Camilo Mejías ◽  
Ingmar Nopens ◽  
...  
Keyword(s):  
Activated Sludge ◽  
Biokinetic Model

Basis for the ICRP’s updated biokinetic model for systemic astatnie

2022 ◽  
Author(s):  
Richard Wayne Leggett ◽  
Caleigh Samuels
Keyword(s):  
Salivary Glands ◽  
Intravenous Injection ◽  
Half Life ◽  
Particle Therapy ◽  
Radiation Hazard ◽  
Radiation Doses ◽  
Tissue Dose ◽  
Biokinetic Model ◽  
Dose Coefficients ◽  
Icrp Publication

Abstract The ICRP recently updated its biokinetic models for workers in a series of reports called the OIR (Occupational Intakes of Radionuclides) series. A new biokinetic model for astatine, the heaviest member of the halogen family, was adopted in OIR Part 5 (ICRP Publication 151, in press). This paper provides an overview of available biokinetic data for astatine; describes the basis for the ICRP’s updated model for astatine; and tabulates dose coefficients for intravenous injection of each of the two longest lived and most important astatine isotopes, 211At and 210At. Astatine-211 (T1/2 = 7.214 h) is a promising radionuclide for use in targeted α-particle therapy due to several favorable properties including its half-life and the absence of progeny that could deliver significant radiation doses outside the region of α-particle therapy. Astatine-210 (T1/2 = 8.1 h) is an impurity generated in the production of 211At in a cyclotron and represents a potential radiation hazard via its long-lived progeny 210Po (T1/2 = 138 d). Tissue dose coefficients for injected 210At and 211At based on the updated model are shown to differ considerably from values based on the ICRP’s previous model for astatine, particularly for the thyroid, stomach wall, salivary glands, lungs, spleen, and kidneys.

DISSOLUTION RATE AND BIOKINETIC MODEL OF ZIRCONIUM TRITIDE PARTICLES IN RAT LUNGS

2010 ◽  
Vol 98 (5) ◽  
pp. 672-682 ◽  
Author(s):  
Yue Zhou ◽  
Yung-Sung Cheng ◽  
Yansheng Wang
Keyword(s):  
Dissolution Rate ◽  
Biokinetic Model ◽  
Rat Lungs

Calculation of Internal Dose and Possible Limits for Intakes of Radionuclides in Case of Plutonium Wounds

2021 ◽  
Vol 65 (6) ◽  
pp. 27-37
Author(s):  
A. Molokanov ◽  
B. Kukhta ◽  
B. Galushkin
Keyword(s):  
Effective Dose ◽  
Systemic Circulation ◽  
Medical Intervention ◽  
Internal Exposure ◽  
Internal Dose ◽  
Regulatory Requirements ◽  
Biokinetic Model ◽  
Prognostic Assessment ◽  
Calculated Dose ◽  
Expert Analysis

Purpose: Assessment of the degree of compliance with the principles of radiation safety and regulatory requirements in case of plutonium wounds. Material and methods: Using a wound intake of plutonium by a worker as an example, issues of the formation of the internal dose due to the wound intake and formal comparison of calculated dose values with regulatory requirements are considered. The calculations are carried out using expert analysis of the experimental data on the urine excretion of plutonium during the observation period of 7 years based on the ICRP model for direct intake into blood. In addition, calculations are carried out using prognostic assessment of the same dose values based on the biokinetic model for radionuclide-contaminated wounds published by NCRP Report No 156 together with the above model of the ICRP for plutonium compounds Strong, Colloids, Particles and Fragment. Results: Based on the calculations, possible annual limits on intakes (ALI) of radionuclides in case of plutonium wounds are derived. As criteria for determining the ALI, dose values were taken that due to the uptake of the radionuclide into the systemic circulation from the wound for any calendar year considered for 50 years after the wound intake of selected plutonium compound. Namely, the committed effective dose; the effective dose implemented in a year and the organ annual equivalent dose (to bone surface and liver). Conclusion: Based on the analysis of the above calculations, the authors formulated the formation features of the employee’s internal exposure due to wound intake of plutonium and recommendations for determining the value of plutonium intake in the wound, evaluating the effectiveness of decorporation therapy and determining the type of radionuclide compound. This allows one to more accurately assess the degree of compliance with regulatory requirements and make an informed decision on the necessary measures of medical intervention and their urgency.

A biokinetic model for nickel released from cardiovascular devices

2016 ◽  
Vol 80 ◽  
pp. 1-8 ◽  
Author(s):  
David M. Saylor ◽  
Lingga Adidharma ◽  
Jeffrey W. Fisher ◽  
Ronald P. Brown
Keyword(s):  
Cardiovascular Devices ◽  
Biokinetic Model
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