Calculation of the radiation doses occurring in the human body for inadvertent ingestion of soil and other soil exposure pathways

We estimate the radiation doses in the human body, in the Gudalore region in India, following the inadvertent ingestion of soil and exposure to other soil pathways by measuring 232Th, 238U, and 40K. We estimate the equivalent dose in eleven different organs and the absorbed dose calculations for the whole body. The annual effective doses are calculated, the lowest is in Kariyasolai at 7.8 × 103 mSv whereas the highest is in Ponnur at 8.9 × 102 mSv. In all regions, the lowest equivalent doses through inadvertent soil ingestion are calculated in the kidney and thyroid whereas the highest doses are in the red marrow and on the bone surface. PACS No.: 87.50.a

Download Full-text

Dose absorbed by technologists in positron emission tomography procedures with FDG

Brazilian Archives of Biology and Technology ◽

10.1590/s1516-89132007000600016 ◽

2007 ◽

Vol 50 (spe) ◽

pp. 129-134 ◽

Cited By ~ 3

Author(s):

Ademir Amaral ◽

Christian Itié ◽

Bernard Bok

Keyword(s):

Positron Emission Tomography ◽

Radiation Safety ◽

Absorbed Dose ◽

Emission Tomography ◽

Whole Body ◽

Skin Dose ◽

Radiation Doses ◽

Dose Equivalent ◽

Positron Emission ◽

Pet Ct

The objective of this work was to evaluate radiation doses delivered to technologists engaged in different tasks involving positron emission tomography (PET) studies with FDG (fluorodeoxyglucose). This investigation was performed in two French nuclear medicine departments, which presented significant differences in their arrangements and radiation safety conditions. Both centers administered about 300 MBq per PET/CT study, although only one of them is a dedicated clinical PET center. Dose equivalent Hp(10) and skin dose Hp(0.07) were measured using Siemens electronic personnel dosimeters. For assessment dose absorbed by hands during drawing up of tracer and injection into the patient, a Polimaster wristwatch gamma dosimeter was employed. Absorbed dose and the time spent during each investigated task were recorded for a total of 180 whole-body PET studies. In this report, the methodology employed, the results and their radioprotection issues are presented as well as discussed.

Download Full-text

Pivotal Role of Dosimetry in High Activity 131i Mibg Therapy in Patients Affected by High Risk Relapsed Refractory Neuroblastoma: Towards a Deeper Metastatic Response Understanding

10.21203/rs.3.rs-152771/v1 ◽

2021 ◽

Author(s):

Bartolomeo Cassano ◽

Milena Pizzoferro ◽

Silvio Valeri ◽

Claudia Polito ◽

Salvatore Donatiello ◽

...

Keyword(s):

High Risk ◽

Clinical Outcome ◽

High Activity ◽

Absorbed Dose ◽

Complete Response ◽

Whole Body ◽

High Dose ◽

Red Marrow ◽

Activity Therapy ◽

Mibg Therapy

Abstract Background: Dosimetry in molecular radiotherapy for personalized treatment is assuming a central role in clinical management of aggressive/relapsed tumors. High-Risk relapsed/refractory metastatic Neuroblastoma (HRrrm-NBL) has a poor prognosis and high-activity 131I-mIBG therapy could represent a promising strategy.The aim of this study was to report the absorbed dose to whole-body (DWB), red marrow (DRM) and lesions (DLesion) correlated to clinical outcome.Methods: 14 patients affected by HRrrm-NBL were treated with high-activity 131I-mIBG therapy (two administrations separated by 15 days). The first administration was weight-based whereas the second one was dosimetry-based (achieving 4 Gy to whole-body). In all patients DWB and DRM has been assessed; 9/14 patients were selected for DLesion evaluation (for a total of 13 lesions). Treatment response was classified in Progression and Stable Disease (PD and SD), Partial and Complete Response (PR and CR) and correlated to the value of DLesion value.Results: The cumulative DWB, DRM and DLesion ranged from [1.49; 4.45], [0.99; 2.56] and [44.17; 585.75] Gy. After treatment 3, 2, 4 and 5 patients showed CR, PR, SD and PD respectively showing a correlation between the clinical outcome and DLesion with a threshold at 80 Gy.Conclusions: Our experience shows feasibility of high activity therapy of 131I MIBG in rrmHR-NBL children as two administration intensive strategy. Dosimetric approach allowed a tailored high dose treatment maximizing the benefits of radionuclide therapy for pediatric patients with a safety profile. The assesment of DLesion contributed to have a deeper understaning of metabolic treatment effects.

Download Full-text

VARIATION SIMULATION OF RADON CONCENTRATION IN THE TISSUES AND ORGANS OF THE BODY BY AN ELECTRICAL CIRCUIT

Radiation Protection Dosimetry ◽

10.1093/rpd/ncz180 ◽

2019 ◽

Vol 187 (3) ◽

pp. 390-401

Author(s):

Milad Pirmoradi ◽

Ali Negarestani ◽

Amin Baghizadeh

Keyword(s):

Cardiac Output ◽

Human Body ◽

Absorbed Dose ◽

Electrical Circuit ◽

The Body ◽

Inert Gases ◽

Inert Gas ◽

Voltage Source ◽

Red Marrow ◽

Inhalation Rate

Abstract In this study, a new model based on electric circuit theory has been introduced to simulate the dynamics of radioactive chemically inert gases in the human body. For this manner, it is assumed that inert gas is transported through the body to various organs via the blood stream. In this simulation, a voltage source is equivalent to gas generation in the atmosphere, the conductivity is equivalent to the cardiac output of the organ, the capacitor capacitance is equivalent to the volume of blood or tissue and voltage across a capacitor is equivalent to the gas concentration in air or blood or a tissue. This simulation can be used to study the dynamics of any inert gas whose partition coefficients are known. We use this simulation to study the dynamics of radon in human body. The physiologically based pharmacokinetic (PBPK) model that describes the fate of radon in systemic tissue has been used for this simulation. Using this simulation, the effective dose equivalent resulting from inhalation of radon has been estimated. The calculated values agree with the previously reported value. Also, using the model, it has been shown that after inhalation of radon gas, absorbed dose has been decreased in different tissues by increasing the inhalation rate without radon. So that, by doubling the inhalation rate and the rate of cardiac output, the value of the absorbed dose has been decreased 11.88% in the adipose tissue, 25.49% in the red marrow tissue and 20.3% in the liver organ.

Download Full-text

Estimating 131I biokinetics and radiation doses to the red marrow and whole body in thyroid cancer patients: probe detection versus image quantification

Radiologia Brasileira ◽

10.1590/0100-3984.2015.0079 ◽

2016 ◽

Vol 49 (3) ◽

pp. 150-157 ◽

Cited By ~ 2

Author(s):

José Willegaignon ◽

Rogério Alexandre Pelissoni ◽

Beatriz Christine de Godoy Diniz Lima ◽

Marcelo Tatit Sapienza ◽

George Barberio Coura-Filho ◽

...

Keyword(s):

Thyroid Cancer ◽

Cancer Patients ◽

Residence Time ◽

Detection Method ◽

Whole Body ◽

Radiation Doses ◽

Average Dose ◽

Image Quantification ◽

Probe Detection ◽

Red Marrow

Abstract Objective: To compare the probe detection method with the image quantification method when estimating 131I biokinetics and radiation doses to the red marrow and whole body in the treatment of thyroid cancer patients. Materials and Methods: Fourteen patients with metastatic thyroid cancer, without metastatic bone involvement, were submitted to therapy planning in order to tailor the therapeutic amount of 131I to each individual. Whole-body scans and probe measurements were performed at 4, 24, 48, 72, and 96 h after 131I administration in order to estimate the effective half-life (Teff) and residence time of 131I in the body. Results: The mean values for Teff and residence time, respectively, were 19 ± 9 h and 28 ± 12 h for probe detection, compared with 20 ± 13 h and 29 ± 18 h for image quantification. The average dose to the red marrow and whole body, respectively, was 0.061 ± 0.041 mGy/MBq and 0.073 ± 0.040 mGy/MBq for probe detection, compared with 0.066 ± 0.055 mGy/MBq and 0.078 ± 0.056 mGy/MBq for image quantification. Statistical analysis proved that there were no significant differences between the two methods for estimating the Teff (p = 0.801), residence time (p = 0.801), dose to the red marrow (p = 0.708), and dose to the whole body (p = 0.811), even when we considered an optimized approach for calculating doses only at 4 h and 96 h after 131I administration (p > 0.914). Conclusion: There is full agreement as to the feasibility of using probe detection and image quantification when estimating 131I biokinetics and red-marrow/whole-body doses. However, because the probe detection method is inefficacious in identifying tumor sites and critical organs during radionuclide therapy and therefore liable to skew adjustment of the amount of 131I to be administered to patients under such therapy, it should be used with caution.

Download Full-text

Occupational radiation exposures for medical workers in Pakistan – An overview

Polish Journal of Medical Physics and Engineering ◽

10.2478/pjmpe-2020-0005 ◽

2020 ◽

Vol 26 (1) ◽

pp. 45-53

Author(s):

Misbah Ahmad ◽

Iftkhar Ahmad ◽

Aakif Ullah Khan ◽

Amin Ali Khan ◽

Kamran Ali Shah ◽

...

Keyword(s):

Occupational Exposure ◽

Whole Body ◽

Radiation Doses ◽

Dose Limit ◽

Annual Dose ◽

Occupationally Exposed ◽

Effective Doses ◽

Personal Dosimetry ◽

Occupational Radiation ◽

Dosimetry Data

AbstractThe imperative use of ionizing radiation in medicine causes the inevitable occupational exposure of the medical workers during the course of routine duties. The magnitude of health risk due to such radiation exposures has been described in terms of occupational radiation doses. In this context, it is obligatory to monitor, measure and document the radiation dose of occupationally exposed medical workers. This study aims to review the whole-body occupational radiation exposures of medical workers in Pakistan. Specifically, online literature published during 2000-2018 was reviewed for the occupational radiation exposures of Pakistani medical workers. Analysis of the extracted personal dosimetry data revealed that the total number of monitored medical occupational workers was 26046. The range of total cumulative and annual average effective doses was 94-15785 Person-mSv and 0.66-7.37 mSv, respectively. A significant number of the workers (25477; ~98%) received an annual dose below 5 mSv, while only 18 workers received an occupational exposure exceeding the annual dose limit of 20 mSv. It is expected that this study will provide a useful reference for evaluating and improving radiation protection and safety policies in the country.

Download Full-text

Research on college gymnastics teaching model based on multimedia image and image texture feature analysis

Discover Internet of Things ◽

10.1007/s43926-021-00015-6 ◽

2021 ◽

Vol 1 (1) ◽

Author(s):

Ying Wu ◽

Jikun Liu

Keyword(s):

Human Body ◽

Rapid Development ◽

Texture Feature ◽

Texture Features ◽

Dynamics Simulation ◽

Image Texture ◽

Whole Body ◽

Database Modeling ◽

Rigid Model ◽

The Subject

AbstractWith the rapid development of gymnastics technology, novel movements are also emerging. Due to the emergence of various complicated new movements, higher requirements are put forward for college gymnastics teaching. Therefore, it is necessary to combine the multimedia simulation technology to construct the human body rigid model and combine the image texture features to display the simulation image in texture form. In the study, GeBOD morphological database modeling was used to provide the data needed for the modeling of the whole-body human body of the joint and used for dynamics simulation. Simultaneously, in order to analyze and summarize the technical essentials of the innovative action, this experiment compared and analyzed the hem stage of the cross-headstand movement of the subject and the hem stage of the 180° movement. Research shows that the method proposed in this paper has certain practical effects.

Download Full-text

Internal dose assessment of 148Gd using isotope ratios of gamma-emitting 146Gd or 153Gd in accidently released spallation target particles

Scientific Reports ◽

10.1038/s41598-020-77718-3 ◽

2020 ◽

Vol 10 (1) ◽

Author(s):

C. Rääf ◽

V. Barkauskas ◽

K. Eriksson Stenström ◽

C. Bernhardsson ◽

H. B. L. Pettersson

Keyword(s):

Operation Time ◽

Isotope Ratios ◽

Dose Assessment ◽

Sensitive Indicator ◽

Whole Body ◽

Internal Dose ◽

Tungsten Target ◽

Alpha Emitter ◽

Spallation Source ◽

Effective Doses

AbstractThe pure alpha emitter 148Gd may have a significant radiological impact in terms of internal dose to exposed humans in case of accidental releases from a spallation source using a tungsten target, such as the one to be used in the European Spallation Source (ESS). In this work we aim to present an approach to indirectly estimate the whole-body burden of 148Gd and the associated committed effective dose in exposed humans, by means of high-resolution gamma spectrometry of the gamma-emitting radiogadolinium isotopes 146Gd and 153Gd that are accompanied by 148Gd generated from the operation of the tungsten target. Theoretical minimum detectable whole-body activity (MDA) and associated internal doses from 148Gd are calculated using a combination of existing biokinetic models and recent computer simulation studies on the generated isotope ratios of 146Gd/148Gd and 153Gd/148Gd in the ESS target. Of the two gamma-emitting gadolinium isotopes, 146Gd is initially the most sensitive indicator of the presence of 148Gd if whole-body counting is performed within a month after the release, using the twin photo peaks of 146Gd centered at 115.4 keV (MDA < 1 Bq for ingested 148Gd, and < 25 Bq for inhaled 148Gd). The corresponding minimum detectable committed effective doses will be less than 1 µSv for ingested 148Gd, but substantially higher for inhaled 148Gd (up to 0.3 mSv), depending on operation time of the target prior to the release. However, a few months after an atmospheric release, 153Gd becomes a much more sensitive indicator of body burdens of 148Gd, with a minimum detectable committed effective doses ranging from 18 to 77 µSv for chronic ingestion and between 0.65 to 2.7 mSv for acute inhalation in connection to the release. The main issue with this indirect method for 148Gd internal dose estimation, is whether the primary photon peaks from 146 and 153Gd can be detected undisturbed. Preliminary simulations show that nuclides such as 182Ta may potentially create perturbations that could impair this evaluation method, and which impact needs to be further studied in future safety assessments of accidental target releases.

Download Full-text

Estimation of Radiation Doses in X-Ray Visualization of Biological Objects

Advanced Materials Research ◽

10.4028/www.scientific.net/amr.880.53 ◽

2014 ◽

Vol 880 ◽

pp. 53-56 ◽

Cited By ~ 6

Author(s):

Sergei Stuchebrov ◽

Andrey Batranin ◽

Dan Verigin ◽

Yelena Lukyanenko ◽

Maria Siniagina ◽

...

Keyword(s):

Radiation Dose ◽

Biological Object ◽

Gas Discharge ◽

Radiation Doses ◽

Semiconductor Detectors ◽

Interior Structure ◽

Dose Calculations ◽

Object Control ◽

X Ray ◽

Biological Objects

Two setups for X-ray visualization of objects interior structure were designed and assembled in TPU. These radiographic systems are based on linear gas-discharge and GaAs semiconductor detectors. During investigation of biological object control of radiation doses has a high priority. In this report radiation dose calculations in X-ray visualization are presented. These calculation also includes dose calculations of sinograms which are used for reconstruction of tomography slices.

Download Full-text