scholarly journals Internal Radiation Dose Assessment in Nuclear Medicine Practices by Using Locally Developed IRDE Software

2019 ◽  
Vol 21 (1) ◽  
pp. 26-30
Author(s):  
Abdus Sattar Mollah ◽  
Mohammad Ruhul Quddus ◽  
Sayeed Mohammad Iqubal
Keyword(s):  
Nuclear Medicine ◽  
Radiation Dosimetry ◽  
Absorbed Dose ◽  
Dose Calculation ◽  
The Body ◽  
Dose Assessment ◽  
Graphic User Interface ◽  
Internal Radiation ◽  
Calculation Methodology ◽  
Bangladeshi Population

In nuclear medicine practices, internal radiation dosimetry offers methods for calculation of radiation absorbed dose and risks from radionuclides incorporated inside the body. To manually perform internal radiation dosimetry is time-consuming and errors can occur in each step leading to developing software tools to ease users. There are many software packages available; however, many of them have limited functions. Locally developed IRDE software has been used to calculate the absorbed dose per unit of radioactivity in the target organ. The dose calculation methodology in nuclear medicine practices is described in this study along with a preliminary result on dose calculation for Bangladeshi population due to ingestion of 131I radioisotope in nuclear medicine practices. IRDE is user-friendly, graphic user interface-based software. It can be performed all steps of internal dosimetry within single environment lead to reducing calculation time and reducing possibility of error. IRDE also provides fast and accurate results which may be useful for a routine work in nuclear medicine facilities. Bangladesh J. Nuclear Med. 21(1): 26-30, January 2018

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.

scholarly journals A comparison of in-air and in-water calibration of a dosimetry system used for radiation dose assessment in cancer therapy

2010 ◽  
Vol 25 (1) ◽  
pp. 51-54 ◽  
Author(s):  
Waheed Arshed ◽  
Khalid Mahmood ◽  
Ikramullah Qazi ◽  
Asad Ullah ◽  
Perveen Akhter ◽  
...  
Keyword(s):  
Radiation Dosimetry ◽  
Absorbed Dose ◽  
Dose Assessment ◽  
Dose Delivery ◽  
Air Kerma ◽  
Tissue Equivalent ◽  
Dosimetry System ◽  
Irradiation Geometry ◽  
Radiation Dose Assessment ◽  
Absorbed Dose To Water

An accurate calibration of the therapy level radiation dosimetry system has a pivotal role in the accuracy of dose delivery to cancer patients. The two methods used for obtaining a tissue equivalent calibration of the system: air kerma calibration and its conversion to a tissue equivalent value (absorbed dose to water) and direct calibration of the system in a water phantom, have been compared for identical irradiation geometry. It was found that the deviation between the two methods remained within a range of 0% to ?1.7% for the PTW UNIDOS dosimetry system. This means that although the recommended method is in-water calibration, under exceptional circumstances, in-air calibration may be used as well.

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.

scholarly journals Hybrid Imaging Reveals Improved Absorbed Dose from Selective Internal Radiation Treatment by Using an Anti-Reflux Catheter

2020 ◽  
Author(s):  
Esmaeel Jafargholi Rangraz ◽  
Xikai Tang ◽  
Geert Maleux ◽  
Jeroen Dekervel ◽  
Eric Van Cutsem ◽  
...  
Keyword(s):  
Hybrid Imaging ◽  
Radiation Treatment ◽  
Standard Procedure ◽  
Absorbed Dose ◽  
Dose Assessment ◽  
Treatment Result ◽  
Activity Measurement ◽  
Internal Radiation ◽  
Dose Volume Histograms ◽  
Selective Internal Radiation

Abstract Selective internal radiation therapy (SIRT) is a promising technique for patients with hepatic malignancies. Several image-based investigations, e.g. volumetric and absorbed dose assessment, are mandatory for SIRT planning and treatment verification based on national and international regulations.General treatment workflows are described in guidelines, recommendations, and the package inserts of the manufactures. But, guidance to tackle particular clinical conditions can be ill-defined and different centers practice their own workflow to analyze the treatment process. This case report includes an example of inconsistency between treatment simulation and observed treatment result, revealed by hybrid imaging. There is no universally accepted standard procedure defined in the literature for detecting and evaluating a possible mismatch between [99mTc]Tc-MAA-based simulation and distribution of the therapeutic microspheres. In this setting, more advanced multi-modal image-based analysis may be beneficial.A 78 year old patient with hepatocellular carcinoma underwent liver radioembolization with resin 90Y-microspheres. Tumoral and non-tumoral dose–volume histograms were evaluated for simulated activity distribution using [99mTc]Tc-MAA-SPECT and post-treatment activity measurement using 90Y-PET. During simulation workup, [99mTc]Tc-MAA particles were administered using a regular catheter. On the other hand, for the treatment session an anti-reflux catheter was used. Our result, suggests that the use of an anti-reflux catheter might improve tumor coverage, and as a result decrease non-tumoral liver uptake deposition.

scholarly journals RadioPharmaDose, a java-based open-source software for estimating and reporting internal radiation doses

2018 ◽  
Vol 16 (1/2) ◽  
pp. 259-266
Author(s):  
Jaafar EL Bakkali ◽  
Hamid Mansouri ◽  
Abderrahim Doudouh
Keyword(s):  
Open Source ◽  
Open Source Software ◽  
Radiation Dosimetry ◽  
Absorbed Dose ◽  
Radiological Protection ◽  
Internal Radiation ◽  
Dosimetric Data ◽  
Sqlite Database ◽  
User Friendly ◽  
Friendly Graphical User Interface

In this work, a user-friendly Java-based open-source software has been developed for internal radiation dosimetry. Based on values published by the International Commission on Radiological Protection (ICRP), the software calculates the estimated absorbed dose for each organ and also the estimated effective dose, this for about forty of the most known radioactive drugs. In addition, the present software offers many features which include: 1) a very friendly graphical user-interface (GUI) designed to facilitate the process of selecting mandatory input data such as radiopharmaceutical product, administered activity and patient's data, 2) a tool for generating a medical report, which can be exported as PDF file or printed directly and then incorporated into the patient's record, 3) a SQLite database for storing patient's specific and dosimetric data. We believe that the present software can be a useful tool for nuclear medicine workers. It is freely available for download on GitHub (https://github.com/EL-Bakkali-Jaafar/RadioPharmaDose).

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

Absorbed-Dose Specification in Nuclear Medicine: Abstract

2002 ◽  
Vol 2 (1) ◽  
pp. 9-9 ◽  
Author(s):  
S. J. Adelstein ◽  
A. J. Green ◽  
R. W. Howell ◽  
J. L. Humm ◽  
P. K. Leichner ◽  
...  
Keyword(s):  
Nuclear Medicine ◽  
Absorbed Dose ◽  
The Body ◽  
Patient Specific ◽  
Dose Rates ◽  
Uniform Distributions ◽  
Medical Internal Radiation Dose ◽  
Medical Dosimetry ◽  
Dose Responses ◽  
Selection Of

A number of reasons have led to a reappraisal of dose specification for nuclear medicine. These include an appreciation of non-uniformities in the distribution of radioactivity in the body, at all levels, for even the most common diagnostic and therapeutic agents; an increasing need to deal with the complexities of varying dose rates; the imperative to provide individual rather than standardised dose estimates as targeted radionuclide therapy becomes more sophisticated; as well as improvements in technology. This Report deals first with biological considerations that inform the rational use of radionuclide dosimetry. Radiobiological factors in the selection of radionuclides and tumour and normal-tissue dose-responses are discussed. Then, the MIRD (medical internal radiation dose) approach to nuclear medical dosimetry, a robust method that has proven its clinical utility, is described. Following on is an elaboration of non-uniform distributions of radioactivity and of varying dose rates. Lastly, the Report deals with techniques and procedures for measuring time variant activity distributions, image fusion, patient specific dose computations, smallscale dosimetry, and the comparison of calculated and measured doses.

scholarly journals Use of IAEA Radiation Dose Criteria to Assess the Need for Internal Radiation Dosimetry in Nuclear Medicine Practices

2018 ◽  
Vol 20 (1) ◽  
pp. 51
Author(s):  
Abdus Sattar Mollah ◽  
K Rahman ◽  
Md Hossain
Keyword(s):  
Nuclear Medicine ◽  
Radiation Dosimetry ◽  
Monitoring Program ◽  
Internal Exposure ◽  
Internal Dosimetry ◽  
Internal Radiation ◽  
A Value ◽  
Effective Doses ◽  
Radioactive Sources ◽  
Occupational Radiation

<p>The IAEA Safety Guide RS-G-1.2 recommends that occupational radiation monitoring should be implemented whenever it is likely that committed effective doses from annual intakes of radionuclides would exceed1mSv. This study presents the analysis of IAEA methodology for the evaluation of the need for the implementation of an internal monitoring program; considering that it should be carried out whenever the potential internal exposure of incorporation leads to a value of annual committed effective dose equal or higher than 1 m Sv. The IAEA criteria applied to commonly used radionuclides in nuclear medicine, taking into consideration usual manipulated unsealed radioactive sources and handling conditions. It is concluded that the handling of unsealed radioactive sources presents the risk of internal radiation exposure to the workers, requiring the implementation of an internal dosimetry program by the concerned Nuclear Medicine Institutes/Centers.  </p><p>Bangladesh J. Nuclear Med. 20(1): 51-55, January 2017  </p>

scholarly journals Features of absorbed radiation doses calculation for cattle’s in Krasnoyarsk krai

2021 ◽  
Vol 215 (12) ◽  
pp. 77-86
Author(s):  
A Fedotova
Keyword(s):  
Radiation Dose ◽  
Absorbed Dose ◽  
Dose Calculation ◽  
Day Length ◽  
Radiation Doses ◽  
Krasnoyarsk Krai ◽  
Ecological Situation ◽  
Internal Radiation ◽  
Regulatory Documents

Abstract. The article provides an adapted methodology of absorbed dose calculation for the cattle from the territories with long-term man-made contamination. The methodology was developed according to existing regulatory documents in the RF: veterinarian rules VR 13.73.13/12-00, VR 13.5.13/03-00, methodical instructions MI 13.5.13-00, regulation for the state veterinarian control system in radioactive contamination of veterinary surveillance objects in the Russian Federation. The aim of the work is the development of calculation methodology of absorbed radiation doses for the cattle on the territory with long-term man-made isotopes contamination, taking to the account the radionuclide composition of the soil. Methods. The regulatory documents governing absorbed doses calculation has been analyzed; the contribution of external and internal radiation into total annual absorbed dose has been determined. Results. It has been established, that the calculation of external radiation dose needs to be done considering doses in stable and pasture periods. Pasture period dose is a sum of day and night doses considering day length. According to the data of radio ecological situation in Krasnoyarsk krai the internal radiation dose should be calculated as a sum of 137Cs, 90Sr, 60Co, taking to the account different concentration of these radionuclides in green and coarse fodder. Scientific novelty. The methodology of dose calculation for the cattle according to the radio ecological situation in Krasnoyarsk krai has been introduced for the first time. Practical significance. This methodology is recommended for the specialists of radiological departments of veterinarian laboratories and science officers in the field of agricultural radiobiology.

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