Internal Dosimetry Modelling for 89Zr-labelled Chimeric Monoclonal Antibody U36 Based on Real Clinical Results

The dynamic of 89Zr-labelled chimeric monoclonal antibody U36 after injection into the human body is modelled based on real clinical results. Results for nine patients (women) from published work is used to create a simple biokinetic model. Cumulative 89Zr Activity in organs and tissues per Bq of administered Activity is calculated with the WinAct program. For the most organs receiving the highest radiation exposure, average absorbed doses were estimated with IDAC 2.1 software. The organs exhibiting the highest dose for adult women were the red bone marrow, lungs, liver, spleen, kidneys, and thyroid (at 1.21,0.837, 0.811, 0.759, 0.745, and 0.411 mGy/MBq, respectively), when the injection was associated with monoclonal antibodies. The results from a new modified biokinetic and modelled calculations are compared with the published experimental diagnostic results conducted in real patients and with given results by OLINDA software, which are in good agreement. Based on real clinical results, the recommended value of blood removing biological time is 65 h for Zr-89 labelled with cMab-U36. © 2020 American Institute of Physics Inc. All rights reserved

Assessment of natural radionuclides and heavy metal concentrations in marine sediments in view of tourism activities in Hurghada city, northern Red Sea, Egypt

The specific activity of 40K, 232Th and 226Ra in marine sediment samples collected from National Institute of Oceanography and Fisheries (NIOF) and Safier Hotel area in Hurghada city (the most important regions in Egypt), were measured by gamma ray spectrometry using NaI(Tl) detector. The values of specific activity varied from 7 ± 1 Bq kg-1 to 53 ± 4 Bq kg-1, 6 ± 1 Bq kg-1 to 32 ± 6 Bq kg-1, and from 167 ± 11 Bq kg-1 to 1120 ± 63 Bq kg-1 for 226Ra, 232Th and 40K, respectively. The heavy metals have been measured and analysed by atomic absorption spectrometer. The major range values of heavy metals concentrations in marine sediment samples were: Cu (10.5-78.0 μg g-1), Zn (21-150 μg g-1), Pb (30-53 μg g-1), Cd (2.50-4.00 μg g-1), Fe (5100-13150 μg g-1), Mn (118-298 μg g-1), Ni (17-36 μg g-1) and Co (16-18 μg g-1). The total organic matter (TOC) and carbonates (CaCo3) distribution have been measured at some locations. Also, the frequency distribution and the value of (232Th/226Ra), (232Th/40K) and (226Ra/40K) ratio for all measured samples were determined. Additionally, evaluations have been made of the radiological hazards and the results are diagrammed by Surfer program in maps. © Penerbit Universiti Sains Malaysia, 2019

Internal Dosimetry assessment for monoclonal antibodies and antibody fragments labeled by Lutetium-177

In this research, the behaviour of monoclonal antibodies (MAbs) and their fragments labeled by 177Lu after injecting into the body is simulated for diagnostic and therapy. The absorbed doses in organs and tissues with maximum radiation exposure are presented. On the base of reference data in the literature, a biokinetic model is built-in for MAb and their fragments. The cumulative activity of 177Lu in organs and tissues per Bq of administered activity is calculated. Spleen, liver, and red bone marrow have the highest doses when 177Lu associated with intact monoclonal antibodies is injected into human body. The estimated doses on these organs are 1.95, 1.17 and 0.54 mGy/MBq, respectively. For the fragments of monoclonal antibodies is considered with 177Lu, the most exposed organs are the kidneys with the doses of 0.78 mGy/MBq for F(ab')) and 1.27 mGy/MBq for F(ab′)2. © 2019 Published under licence by IOP Publishing Ltd

Radiopharmaceutical dose distribution in different organs and tissues for Lu-177 with different carrier

177Lu refers to rare earth elements from a group of lanthanides. Relative to its short time span, 177Lu has virtually pervaded all areas of in vivo radionuclide therapy and becomes one of important keys for therapeutic radionuclides of choice for targeted radionuclide therapy. The rising interest in the use of 177Lu in targeted molecular therapies has primarily developed from recent unmatched advances in molecular and cell biology, which include the use of peptides targeted to cell surface receptors, which are overexpressed on the surface of tumour cells. Therefore, the use of 177Lu-labelled radiopharmaceuticals have been the major factors evoking excitement among researchers and capturing the imagination of the clinical community thanks to advances in molecular and cellular biology. In this work, radiopharmaceutical comparison for 177Lu absorbed dose in health human organs and tissues is presented. The comparison between unlabelled 177Lu (ionic form) and labelled with 177Lu-MDP (methylenediphosphonate) and 177Lu-MAb (monoclonal antibodies). The biokinetic model in each case are described and presented. The absorbed dose in health human organs and tissues are simulated with two recommended programs WinAct and IDAC 2.1(Internal Dose Assessment by Computer) software. The distribution of absorbed dose in the main organs nearly the same with different in the value for the ionic form and 177Lu-MDP. The absorption in the case of ionic form is high. The distribution is completely change while 177Lu-MAb is used. The most absorbed dose fraction goes to spleen and liver unlike bone surface absorb nearly 50 % of dose. © 2019 Author(s)

ICP-OES Elemental Variation on Bottled Drinking Water

The work describes ICP-OES elemental variation (Be, B, Al, Cr, Mn, Fe, Co, Ni, Cu, Zn, As, Se, Mo, Ag, Cd, Sb, Ba,Sn, and Pb) in bottled drinking water.Special thanks for stuff in Faculty of Sciences, Al-azhar university

DETERMINATION OF LANTHANIDES IN PHOSPHATE ROCKS BY INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS

Neutron activation analysis is the most used analytical technique for the determination of the rare-earth elements in geological matrices on account of its high sensitivity, of the possi-bility of determining all the elements and of the undisputed accuracy and reliability of its results.The authors would like to thank Associate professor/ Aleksey V Nastavkin, Institute of the earth sciences in the Southern Federal University

A rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX Monte Carlo code

Half Value Layer calculations theoretically need prior specification of linear attenuation calculations, since the HVL value is derived by dividing ln(2) by the linear attenuation coefficient. The purpose of this study was to establish a direct computational model for determining HVL, a vital parameter in nuclear radiation safety studies and shielding material design. Accordingly, a typical gamma-ray transmission setup has been modeled using MCNPX (version 2.4.0) general-purpose Monte Carlo code. The MCNPX code's INPUT file was designed with two detection locations for primary and secondary gamma-rays, as well as attenuator material between those detectors. Next, Half Value Layer values of some well-known gamma-ray shielding materials such as lead and ordinary concrete have been calculated throughout a broad gamma-ray energy range. The outcomes were then compared to data from the National Institute of Standards and Technology. The Half Value Layer values obtained from MCNPX were reported to be highly compatible with the HVL values obtained from the NIST standard database. Our results indicate that the developed INPUT file may be utilized for direct computations of Half Value Layer values for nuclear safety assessments as well as medical radiation applications. In conclusion, advanced simulation methods such as the Monte Carlo code are very powerful and useful instruments that should be considered for daily radiation safety measures. The modeled MCNPX input file will be provided to the scientific community upon reasonable request. © 2022 Korean Nuclear SocietyPrincess Nourah Bint Abdulrahman University, PNU: PNURSP2022R149This work was performed under Princess Nourah bint Abdulrahman University Researchers Supporting Project Number (PNURSP2022R149), Princess Nourah bunt Abdulrahman University, Riyadh, Saudi Arabia. The authors express their sincere gratitude to Princess Nourah bint Abdulrahman University

The Status of Natural Radioactivity and Heavy Metals Pollution on Marine Sediments Red Sea Coast, At Safaga, Egypt

Natural 226Ra, 232Th and 40K radio nuclides concentration in beach Sediments along Safaga coast of Red sea, Egypt has been carried out using a NaI (Tl) gamma ray spectrometric technique. The total average concentrations of radionuclides ± uncertainty of 226Ra, 232Th and 40K were 22.2 ± 1.7, 19.2 ± 2.5, and 477.6 ± 27.6 Bqkg-1, respectively. The total average absorbed dose rate is found to be 41.4 nGyh-1, whereas the annual effective dose rate has an average value of 54 μSvy-1. The total organic matter (TOC), carbonates (CaCo3) and Heavy metals distribution have been measured at some locations, the concentration for the investigated heavy metals overtake the allowable limits recommended by the Canadian Environmental Quality Guidelines, this assigned to the ratio of metals pollution is caused by anthropogenic activities (phosphate shipment as in Abu Tartour harbor and navigation as in Touristic harbor) and or by natural impacts such in mangrove interment. Statistical analyses were carried out between the parameters obtained from the radioactivity to know the existing relations and to study the spatial distribution of radionuclide

RADIUM MEASUREMENTS IN GROUNDWATER FROM THE CENTRAL REGION OF SAUDI ARABIA USING GAMMA SPECTROMETRY PRECEDED BY ION EXCHANGE

Naturally accruing radioactive materials in the environment have received recently atten-tion. There is a lack of risk assessment regarding the radioactive materials contamination in agricultural environments in Qassim region in the central region of Saudi Arabia

INTERNAL ORGANS DOSIMETRY OF 89Zr IN MICE UTILIZING BIODISTRIBUTION OF 89Zr-DFO-TRASTUZUMAB, Zr-OXALATE AND Zr-CHLORIDE: PROMISING BIOKINETIC MODEL

The present investigation focuses on the accumulative activity and absorbed dose of 89Zr in mice to present Human Biokinetic model