ESTIMATION OF HUMAN DOSE OF 188/186RE-HEDP COCKTAIL BASED ON OLINDA/EXM AND DISTRIBUTION DATA IN RATS

2020 ◽  
Vol 190 (2) ◽  
pp. 158-164
Author(s):  
Zahra Pourhabib ◽  
Hassan Ranjbar ◽  
Ali Bahrami Samani

Abstract 188Re and 186Re are two applicable rhenium medical radioisotopes with complementary features that make them beneficial for different sizes of tumours. The aim of this study is to investigate 188/186Re-HEDP efficacy as a cocktail by calculating absorbed radiation dose in human organs based on biodistribution data obtained by injecting it to normal rats. Three rats were sacrificed at different time intervals and the percentage of injected dose per gram of each organ was measured by direct counting from rat data. By calculating accumulated activities in each organ and extrapolating rat data to human data by the radiation dose assessment resource method and by using OLINDA/EXM software, the injected dose in various human organs was obtained. The calculated absorbed dose showed that the 188/186Re-HEDP has noticeable properties that can be more helpful in comparison with using each of the rhenium radioisotopes separately.

2019 ◽  
Vol 2019 ◽  
pp. 1-5 ◽  
Author(s):  
Kfier Kuba ◽  
Diana Wolfe ◽  
Alan H. Schoenfeld ◽  
Anna E. Bortnick

There is a gap in the literature regarding fetal radiation exposure from interventional cardiac procedures. With an increasingly large and complex cohort of pregnant cardiac patients, it is necessary to evaluate the safety of invasive cardiac procedures and interventions in this population. Here we present a case of a patient with multiple medical comorbidities and non-ST elevation myocardial infarction (NSTEMI) at 15 weeks’ gestation, managed with percutaneous coronary intervention (PCI). We were able to minimize the maternal and estimated fetal absorbed radiation dose to <1 milliGray (mGy), significantly less than the threshold dose for fetal adverse effects at this gestational age.


2015 ◽  
Vol 40 (2) ◽  
pp. 102 ◽  
Author(s):  
Samaneh Zolghadri ◽  
AmirReza Jalilian ◽  
Hassan Yousefnia

Blood ◽  
2004 ◽  
Vol 104 (11) ◽  
pp. 1162-1162 ◽  
Author(s):  
Jane N. Winter ◽  
David J. Inwards ◽  
Stewart Spies ◽  
Gregory Wiseman ◽  
David Patton ◽  
...  

Abstract Twenty-eight patients with relapsed or refractory CD20+ NHL have been enrolled in an ongoing phase I trial of dose-escalated 90YZ followed by high-dose BEAM and autotransplant in which the 90YZ dose is patient-specific based on dosimetry. 90YZ doses are calculated to deliver cohort-defined radiation doses (100, 300, 500, ... cGy) to critical organs (liver, lung or kidney), with 3–6 patients per group. On D -22, rituximab (R) 250 mg/m2 is infused followed by the imaging dose of 111In Zevalin® (5 mCi). Imaging is performed immediately post-injection and at 4, 24, 72, and 144 hours; dosimetry is performed on D -15. On D -14, R 250 mg/m2 is administered followed immediately by 90YZ at the dose calculated to deliver the cohort-prescribed absorbed radiation dose to the critical organ. On D -6 through -1, patients receive high-dose BEAM. On D0, a minimum of 2.0 X 106 CD34+ cells/kg is infused and G-CSF 5 μg/kg SQ daily begun. The median age was 54 (range: 25–72) years. NHL histologic subtypes were as follows: mantle cell 5, diffuse aggressive 13, low grade 5, and transformed 5. Most had received 3 or more treatment regimens, including R. The toxicity profile was similar to that associated with high-dose BEAM and included a decrease in DLCO for most patients with one patient at the 500 cGy dose level experiencing a transient decline to below 50% of the predicted value corrected for hemoglobin. The most common grade III/IV toxicities were infection, fever, stomatitis, nausea, vomiting, diarrhea, hemorrhage, and edema. One patient experienced transient veno-occlusive disease at the 700 cGy dose level. Engraftment occurred at a median of 10 days (range:8–18) to granulocytes ≥ 500/μL, and 21 days (range:13–40days) to platelets ≥20,000/μL . With a median follow-up of one year, the 3 year overall and progression-free survivals are 60% and 50%, respectively. Figure Figure 90-Y Zevalin Dosing by Cohort (median; range) Cohort (cGy) Total Dose (mCi) mCi/kg 100 (n=3) 5 (2–14) .06(.05–.12) 300 (n=7) 22(14–57) .25(.18–.63) 500 (n=6) 31(16–48) .40(.14–.63) 700 (n=6) 37(26–55) .38(.27–.73) 900 (n=3) 28(27–37) .32(.27–.44) 1100 (n=3) 48(29–65) .57(.50–.75) The liver was the critical organ in nearly all cases. Patient-specific doses calculated to deliver a cohort-prescribed absorbed radiation dose to the critical organ were highly variable suggesting that dosing based on weight and not dosimetry is likely to result in a wide range of absorbed dose to critical organs. In the context of this study, 90YZ has been administered to eight patients at doses of .5 mCi/kg or greater. We conclude that with careful dosimetry, 90YZ doses higher than the conventional .4 mCi/kg may be safely combined with BEAM and autotransplant. Accrual continues at the 1300 cGy dose level.


2018 ◽  
Vol 18 (1) ◽  
pp. 70-74
Author(s):  
Ali Rabiei ◽  
Hassan Yousefnia ◽  
Samaneh Zolghadri ◽  
Mojtaba Shamsaei

AbstractAimBone-seeking radiopharmaceuticals are potential therapeutic tools for bone marrow ablation in patients with multiple myeloma. In this procedure, estimation of radiation absorbed dose received by the target and non-target organs is one of the most important parameters that should be undertaken. This research revolves around the absorbed dose to human organs after 90Y-BPAMD injection.Materials and methods90Y-(4-{[(bis(phosphonomethyl))carbamoyl]methyl}-7,10-bis(carboxymethyl)-1,4,7,10-tetraazacyclododec-1-yl) acetic acid (90Y-BPAMD) complex was successfully prepared under optimised conditions. The human absorbed dose of the complex was estimated based on the biodistribution data on rats using the radiation-absorbed dose-assessment resource method. The target to non-target absorbed dose ratios for the complex was compared with the ratios for 166Ho-DOTMP, as the main radiopharmaceutical for bone marrow ablation.ResultsAs expected, the highest amounts of absorbed dose were observed in the bone surface and the bone marrow with 2·52 and 2·29 mGy/MBq, respectively. The red marrow to the most organ absorbed dose ratios for 90Y-BPAMD are much higher than the ratios for 166Ho-DOTMP.Findings90Y-BPAMD has interesting characteristics compared with 166Ho-DOTMP and can be considered as a high potential agent for bone marrow ablative therapy of the patient with multiple myeloma.


2013 ◽  
Vol 4 (1) ◽  
pp. 135-143
Author(s):  
AHMR Quddus ◽  
M Moksed Ali ◽  
MMA Zaman ◽  
AS Mollah

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


2020 ◽  
Vol 35 (1) ◽  
pp. 56-63
Author(s):  
Bojan Rankovic ◽  
Nikolina Nikolic ◽  
Slobodan Masic ◽  
Ivica Vujcic

The distribution of the absorbed dose within the irradiated product is a complex function of the product density and homogeneity, the position and shape of the radiation source, as well as the design of the irradiator. In this paper, detailed mapping of absorbed radiation doses in products of different density: gauze, plastic, and soil, is performed. Positions of minimum and maximum absorbed radiation dose were determined, and the homogeneity of irradiation of products was calculated using the ethanol-monochlorobenzene oscillotitrator dosimetry system.


Author(s):  
Tumpal Pandiangan ◽  
Ika Bali

Direct measurement of each radiation dose to the patient's organs is not possible. In general, to estimate the dose absorbed by human organs is approached by measurements in human phantoms, but this approach is still too rough because the composition of phantoms is not easily made the same as the actual organ composition. Currently, for important matters such as the accuracy of determining the absorption dose by human organs, the Monte Carlo simulation method (MCNP) with special software is used. This has led to a growing desire for scientists to make the transition from using phantoms to computing software for medical physics applications. However, until now no comprehensive document has been written to introduce the use of the MCNP program to simulate its application in medical physics. The purpose of this study was to analyze the absorbed dose of gamma radiation in tumor tissue in the breast by simulating changes in distance and tumor size using the MCNP-5 program. This can be useful in ensuring the application of radiation protection to the patient and the environment in which the patient is located. The results showed that the radiation dose in cell 1 (tumor tissue) with a change in the distance between the radiation source and cell 1 was getting bigger, resulting in a decrease in the dose in cell 1, while the effect of cell volume 1 was greater, the greater the dose received by cell 1. In addition, through this simulation it can be seen that for each addition of 1 cm3 the volume of cell 1 for tumor tissue can increase the absorption energy by 3.5x10e-12 Gray. Keywords: MCNP-5; simulation; radiation dose; tumor tissue AbstrakPengukuran setiap dosis radiasi pada organ pasien tidak dimungkinkan secara langsung. Pada umumnya untuk memperkirakan dosis yang diserap oleh organ tubuh manusia didekati dengan pengukuran pada phantom manusia, namun pendekatan ini juga masih terlalu kasar karena komposisi phantom tidak mudah dibuat sama dengan komposisi organ yang sebenarnya. Sehingga saat ini, untuk hal-hal yang penting seperti ketepatan penentuan dosis serap oleh organ tubuh manusia, digunakan metode simulasi Monte Carlo (MCNP) dengan perangkat lunak khusus. Hal ini mendorong meningkatnya keinginan para ilmuwan melakukan transisi dari penggunaan phantom ke penggunaan komputasi perangkat lunak untuk aplikasi fisika medis. Namun sampai saat ini belum tersedia dokumen komprehensif yang ditulis untuk memperkenalkan penggunaan program MCNP guna mensimulasikan aplikasinya dalam fisika medis. Tujuan penelitian ini adalah menganalisis dosis serap radiasi gamma pada jaringan tumor di payudara melalui simulasi perubahan jarak dan besar tumor menggunakan program MCNP-5. Hal ini dapat berguna dalam memastikan penerapan proteksi radiasi pada pasien dan lingkungan tempat pasien. Hasil penelitian menunjukkan dosis radiasi pada sel 1 (jaringan tumor) dengan perubahan jarak antara sumber radiasi dengan sel 1 semakin besar, mengakibatkan besar dosis di sel 1 semakin menurun, sedangkan pengaruh volume sel 1 yang semakin besar maka dosis yang diterima sel 1 semakin besar juga. Selain itu, melalui simulasi ini dapat diketahui untuk setiap penambahan 1 cm3 volume sel 1 jaringan tumor dapat meningkatkan energi serap sebesar 3,5x10e-12 Gray.


2020 ◽  
Author(s):  
Nurul Fitriyah ◽  
Rahmatul Izza Nur Amalia ◽  
Bambang Haris Suhartono ◽  
Suryani Dyah Astuti

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