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 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 Standard Radiation Dosimetry Models: What Interventional Radiologists Need to Know

2021 ◽  
Vol 38 (04) ◽  
pp. 405-411
Author(s):  
Linzi Arndt Webster ◽  
Alexander Villalobos ◽  
Bill S. Majdalany ◽  
Zachary L. Bercu ◽  
Ripal T. Gandhi ◽  
...  
Keyword(s):  
Clinical Practice ◽  
Radiation Dosimetry ◽  
Single Case ◽  
Internal Radiation ◽  
Liver Cancers ◽  
Y90 Radioembolization ◽  
Dose Model ◽  
The Difference ◽  
Medical Internal Radiation Dose ◽  
Yttrium 90

AbstractThoughtful and accurate dosimetry is critical to obtain the safest and most efficacious yttrium-90 (Y90) radioembolization of primary and secondary liver cancers. Three dosimetry models are currently used in clinical practice, namely, body surface area model, medical internal radiation dose model, and the partition model. The objective of this review is to briefly outline the history behind Y90 dosimetry and the difference between the aforementioned models. When applying these three models to a single case, the differences between them are further demonstrated. Each dosimetry model in clinical practice has its own benefits and limitations. Therefore, it is incumbent upon practicing interventional radiologists to be aware of these differences to optimize treatment outcomes for their patients.

scholarly journals STUDI AWAL ESTIMASI DOSIS INTERNAL 177Lu-DOTA TRASTUZUMAB PADA MANUSIA BERBASIS UJI BIODISTRIBUSI PADA MENCIT

2015 ◽  
Vol 16 (2) ◽  
pp. 105
Author(s):  
Nur Rahmah Hidayati ◽  
Sri Setyowati ◽  
Mrs Sutari ◽  
Mrs Triningsih ◽  
Mr Karyadi ◽  
...  
Keyword(s):  
Radiation Dose ◽  
Residence Time ◽  
Reference Model ◽  
Preclinical Study ◽  
Internal Dosimetry ◽  
Internal Dose ◽  
Internal Radiation ◽  
Human Organ ◽  
Biodistribution Data ◽  
Her 2

ABSTRAK STUDI AWAL ESTIMASI DOSIS INTERNAL 177Lu-DOTA TRASTUZUMAB PADA MANUSIA BERBASIS UJI BIODISTRIBUSI PADA MENCIT. Radiofarmaka baru untuk pengobatan penyakit kanker payudara tipe HER-2, 177Lu-DOTA Trastuzumab, telah berhasil diproduksi oleh Pusat Teknologi Radioisotop dan Radiofarmaka (PTRR) BATAN. Demi keamanan produk dan keselamatan pasien, radiofarmaka baru tersebut perlu dilengkapi dengan data studi dosis internal yang dilakukan setelah uji praklinis pada hewan coba selesai. Oleh karena itu, studi ini bertujuan untuk melakukan estimasi dosis pada pasien yang dihitung berdasarkan data uji biodistribusi pada mencit. Studi Uji biodistribusi dilakukan pada 25 ekor mencit dan diamati biodistribusinya pada organ-organ, diantaranya otak, perut, usus, jantung , ginjal, hati, paru-paru, otot, tulang, limpa dan kandung kemih. Pengamatan cacahan organ dilakukan pada jam ke 1, 2, 3, 4, 24, 48 pasca injeksi radiofarmaka 177Lu DOTA-Trastuzumab sebesar 100mCi. Hasil yang diperoleh dari uji biodistribusi adalah % ID/gram organ tikus, kemudian dilakukan konversi perhitungan ke % ID/gram organ manusia. Untuk mengestimasi dosis ke manusia, hasil %ID/gram organ tersebut dipakai sebagai input pada software dosimetri internal OLINDA/EXM, dengan cara melakukan plotting %ID/gram versus waktu, yang akan menghasilkan residence time di masing-masing organ. Setelah residence time diperoleh, dosis internal radiasi pada masing-masing organ dan seluruh tubuh dapat diketahui. Hasil studi menunjukkan bahwa tiga  organ yang memiliki dosis internal tertinggi 177Lu DOTA Trastuzumab adalah : paru-paru, hati dan ovarium dengan dosis masing-masing 0,063; 0,046 dan 0,025 mSv/MBq. Disimpulkan bahwa hasil estimasi dosis internal radiasi total yang diperoleh manusia pada penyuntikan radiofarmaka 177Lu-DOTA Trastuzumab adalah 0.21 mSv/MBq. ABSTRACT   INTERNAL DOSE ESTIMATION OF 177Lu-DOTA TRASTUZUMAB IN HUMAN BASED ON THE BIODISTRIBUTION DATA OF MICE: A PRELIMINARY STUDY. A new radiopharmaceutical for treating Breast Cancer of HER-2 type, 177Lu DOTA-Trastuzumab, had been successfully produced by The Centre for Radioisotope and Radiopharmaceutical Technology-BATAN. With regard to the patient safety, the new drug development process need internal dosimetry data obtained of preclinical study in animal. Hence, this study has been objected to estimate the internal radiation dose in human by performing the biodistribution test in mice. In this study, the biodistribution test was done for 25 mice and sacrificed at 1, 2, 3, 4, 24, 48 hour after the injection of 177Lu DOTA-Trastuzumab. There were 11 organs, namely brain, stomach, intestine, heart, kidneys, liver, lungs, muscle, bone, spleen, and urinary bladder, have been investigated by observing the uptake in each organ during the proposed time. The result of biodistribution test then were being calculated into injection dose per gram human organ (%ID/gr). To estimate the internal dose in human, the data of % ID/gram in human need to be plotted to calculate the residence time which will be need as the input for OLINDA/EXM, a tool for calculating internal dosimetry in Nuclear Medicine fields. As a result, three organs that have been estimated receiving the highest internal radiation dose due to the administration of 177Lu DOTA Trastuzumab are: lungs, liver, and ovaries at approximately 0,063; 0,046 and 0,025 mSv/MBq respectively. To conclude, the total internal dose in human reference model due to the administration of 177Lu-DOTA Trastuzumab has been estimated to be 0,21 mSv/MBq.

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 Application Of 99m Tc Radioisotope In Diagnostic Procedures And Internal Radiation Dose Estimation

KnE Energy ◽  
2016 ◽  
Vol 1 (1) ◽  
Author(s):  
Nur Rahmah Hidayati
Keyword(s):  
Nuclear Medicine ◽  
Radiation Dose ◽  
Diagnostic Procedures ◽  
Dose Assessment ◽  
Internal Dose ◽  
Dose Estimation ◽  
Internal Radiation ◽  
Medicine Department ◽  
Foreign Countries ◽  
Organ Level

At about 70% of nuclear medicine procedures have utilized <sup>99m</sup>Tc in their clinical practices.This has lead <sup>99m</sup>Tc becoming the most convenient radioisotope in nuclear medicine diagnostic. To estimate the internal radiation dose due to the administration of <sup>99m</sup>Tc to the patients, only few documents from International Commission of Radiation Protection (ICRP) have been available.  However, the calculation usually has applied Caucasian data in Standard Reference Man as a model. The objective of this study was to review the application of <sup>99m</sup>Tc in Indonesia and to compare the internal dose estimation for <sup>99m</sup>Tc procedures by using Organ Level Internal Dose Assessment/ EXponential Modeling (OLINDA/EXM) software. The result of calculation was compared between Adult Caucasian model and Asian Reference Man. The result shows that <sup>99m</sup>Tc has been well applied and developed for diagnostic procedures in Nuclear Medicine Department. Moreover, in most diagnostic procedures using <sup>99m</sup>Tc in Indonesia, adult patients will receive effective dose about 1-15% higher than adult patient in foreign countries which apply the Caucasian model. Hence, to estimate the similar stochastic risk from the same procedure, the maximum value in recommended administered dose should be avoided and need to be evaluated.

scholarly journals Assessment of internal radiation exposure of nuclear medicine workers using whole body gamma counter

2020 ◽  
Vol 1497 ◽  
pp. 012026
Author(s):  
A Norhayati ◽  
M S Suzilawati ◽  
Z Nur Khairunisa ◽  
Y T L Raymond ◽  
A Azimawati
Keyword(s):  
Nuclear Medicine ◽  
Radiation Exposure ◽  
Whole Body ◽  
Internal Radiation ◽  
Gamma Counter

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.

Determination of Resistance to Abrasive Wear. VIII. Influence of Softeners in Tests with the Akron-Croydon and Du Pont Machines

1949 ◽  
Vol 22 (1) ◽  
pp. 259-262
Author(s):  
J. F. Morley
Keyword(s):  
Unit Area ◽  
Published Data ◽  
The Road ◽  
Abrasive Surface ◽  
Abrasive Power ◽  
The Difference ◽  
On The Road ◽  
The Right ◽  
Abrasion Testing

Abstract These experiments indicate that softeners can influence abrasion resistance, as measured by laboratory machines, in some manner other than by altering the stress-strain properties of the rubber. One possible explanation is that the softener acts as a lubricant to the abrasive surface. Since this surface, in laboratory abrasion-testing machines, is relatively small, and comes repeatedly into contact with the rubber under test, it seems possible that it may become coated with a thin layer of softener that reduces its abrasive power. It would be interesting in this connection to try an abrasive machine in which a long continuous strip of abrasive material was used, no part of it being used more than once, so as to eliminate or minimize this lubricating effect. The fact that the effect of the softener is more pronounced on the du Pont than on the Akron-Croydon machine lends support to the lubrication hypothesis, because on the former machine the rate of wear per unit area of abrasive is much greater. Thus in the present tests the volume of rubber abraded per hr. per sq. cm. of abrasive surface ranges from 0.03 to 0.11 cc. on the du Pont machine and from 0.0035 to 0.0045 cc. on the Akron-Croydon machine. On the other hand, if the softener acts as a lubricant, it would be expected to reduce considerably the friction between the abrasive and the rubber and hence the energy used in dragging the rubber over the abrasive surface. The energy figures given in the right-hand columns of Tables 1 and 3, however, show that there is relatively little variation between the different rubbers. As a test of the lubrication hypothesis, it would be of interest to vary the conditions of test so that approximately the same amount of rubber per unit area of abrasive is abraded in a given time on both machines; this should show whether the phenomena observed under the present test conditions are due solely to the difference in rate of wear or to an inherent difference in the type of wear on the two machines. This could most conveniently be done by considerably reducing the load on the du Pont machine. In the original work on this machine the load was standardized at 8 pounds, but no figures are quoted to show how abrasion loss varies with the load. As an addition to the present investigation, it is proposed to examine the effect of this variation with special reference to rubbers containing various amounts and types of softener. Published data on the influence of softeners on the road wear of tire rubbers do not indicate anything like such large effects as are shown by the du Pont machine. This throws some doubt on the value of this machine for testing tire tread rubbers, a conclusion which is confirmed by information obtained from other workers.

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