Radiological characterization of the irt-5000(14-Tammuz) research nuclear reactor at Al-Tuwaitha nuclear center in Iraq

Al-Alawy, Iman Tarik; Mzher, Osama Abdulameer

doi:10.1007/s12665-019-8122-6

Cited by 6 publications

(3 citation statements)

References 7 publications

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“…The limits radiation concentration of the walls, ground and ceiling were within the limits of the radiation background. These results agreed with the findings of the researcher Radiological Characterization and Safety Assessment of Destroyed Nuclear Facilities at Al-Tuwaitha Nuclear Site in Iraq [10].…”

Section: Discussionsupporting

confidence: 90%

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Measurement of Radioactive Concentrations and Determination of Isotopes Using Portable Devices for Radiochemistry Laboratories Al-Tuwaitha Nuclear Site in Iraq

Fadhil

Al-Alawy

Al-Nasri

2022

Al-Mustansiriyah Journal of Science

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The measurements of radioactive concentrations using portable radiological devices for radiochemistry laboratories at the Al-Tuwaitha nuclear site (section C) were studied, section C consists of three laboratories, C1, C2, and C3 were used, Redeye device to measure the radioactive concentrations of alpha and beta emitters, and the Interceptor™ Specifications device to detect radioisotopes. The results showed the presence of radioactive contamination in Unit C distributed over most of its parts. In the C1 laboratory, the highest radioactive contamination was recorded in HCL2 with a concentration of 113.65Bq/cm2. In addition, the C2 laboratory recorded the highest radioactive concentration in FH1 with a concentration of 830.14Bq/cm2 for Beta particle emitters, while the C3 laboratory recorded the highest pollution in FH contamination with a radioactive concentration of 75.26 Bq/cm2. The results show that location C shows the isotopes detected in the laboratory components, such as Cesium 137Cs, Neptunium 237Np, and Americium 241Am. The results showed the presence of contamination on the laboratory floor in the fourth part, contaminated with Americium 241Am and Lutetium 167Lu isotopes. While location B did not record radioactive contamination in most of its parts except for room B8 which recorded radioactive concentrations of about 1.33 Bq/cm2. While location A, that is, no radioactive contamination was recorded, and the readings were within the permissible limits

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Section: Discussionsupporting

confidence: 90%

“…Laboratory C2 contains 11 glove boxes (GB1, GB2, GB3, GB4, GB5, GB6, GB7, GB8, GB9, GB10, and GB11) and two fume hoods. Laboratory C3 includes one fume hood [10].…”

Section: Radiological Characterization In Radiochemistry Laboratoriesmentioning

confidence: 99%

Measurement of Radioactive Concentrations and Determination of Isotopes Using Portable Devices for Radiochemistry Laboratories Al-Tuwaitha Nuclear Site in Iraq

Fadhil

Al-Alawy

Al-Nasri

2022

Al-Mustansiriyah Journal of Science

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“…As a result, there was huge looting of materials like equipment, some amount radioactive contamination occurred, and there was damage associated with many facilities. Information on distribution of radionuclide and radiation concentration in the environment is pivotal for detecting the terrestrial radiation exposure effects due to cosmogenic and human activities [11,12]. In this study, three important facilities were chosen in In addition, the control groups included 13 apparently healthy volunteers, randomly chosen from the population living in Baghdad, far away from the Al-Tuwaitha Nuclear Research Site.…”

Section: Introductionmentioning

confidence: 99%

Determination of Activity Concentrations and Internal Dose Assessments in Urine from Workers in Iraqi Nuclear Research Center, Iraq

Firdows Sami Hussein,

Muhannad Alrakabi,

Abdulsahib Kadhim Ali

et al. 2024

cbej

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To detect tritium levels in the human body, tritium in the urine must be measured. The investigation of the level of tritium activity in the urine of workers of the Iraqi Nuclear Research Center (INRC) has been realized in order to assess vocational exposure levels. Three worker groups in INRCs were chosen, involved in the Central Laboratories Directorate (CLD), the Decommissioning Directorate (DD), and the Radioactive Waste Treatment and Radioactive Waste Store Directorate (WTWSD), among others in Al-Tuwiatha site, in addition to the control group, as the research targets. Tritium concentration was determined in urine samples from 52 workers (aged 32-61) and 13 control people (aged 30-58). 65 urine samples of 50 mL were collected and analyzed. The Eichrom's Tritium Column way was used to handle the samples of urine, and the distillate tritium activity concentration was then assessed using Liquid Scintillation Counter. The effective and annual effective doses were estimated for the internal doses. The accuracy of urine sample measurements had been tested. The highest level of tritium activity samples of urine from three groups of workers in INRCs is 65.401 Bq/L, and for control group is 39.300 Bq/L, activity of tritium concentrations estimated by using counting scintillation of liquid (LSC) were found to be lower than Minimum Detectable Activity (MDA) of 1.95 Bq/L. The effective and annual effective dose from tritium was also assessed depend on results measured previously and standard values adapted by the International Commission on Radiological Protection. The effective highest doses for workers groups and control group were 497.048 ×10-3 and 298.680×10-3 nSv respectively. Highest annual effective dose 5757.773×10-3 and 5167.042×10-3 nSv respectively. These results were lowest than the allowed effective dose for the workers.

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Decontamination of actual radioactive wastewater containing 137Cs using bentonite as a natural adsorbent: equilibrium, kinetics, and thermodynamic studies

Muslim¹,

Albayati

Al-Nasri

2022

Sci Rep

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Batch adsorption treatment using Iraqi bentonite as a natural adsorbent was adopted in this study to decontaminate actual 137Cs radioactive wastewater from the Al-Tuwaitha Nuclear Research Center, located south of Baghdad. The bentonite characterization was applied before and after treatment, using chemical compositions analyses, X-ray diffraction (XRD), scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDX), Brunauer–Emmett–Teller (BET) surface area analysis and Fourier-transform infrared spectroscopy (FT-IR). The batch adsorption mode was applied with the initial radioactivity concentration (1440.5 Bq/L), solid/liquid ratio (1 g/L), pH (6–8), contact time (1.5 h), and temperature (298°K). The adsorption experiments showed a decontamination removal efficiency of about 95.66% of 137Cs. A Freundlich adsorption isotherm model was approved for the adsorption of 137Cs, with a coefficient of determination R2 = 0.998. A pseudo-second-order model fitted well with the adsorption of 137Cs, with R2 = 0.983. The positive value of ΔH° in the thermodynamic results indicated that the adsorption process was endothermic physisorption (ΔH° = 15.01 kJ mol−1), spontaneous and favorable (ΔG° = −7.66 kJ mol−1 K−1), with a very low degree of disorder (ΔS° = 0.076 kJ mol−1 K−1).

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Radiological characterization of the irt-5000(14-Tammuz) research nuclear reactor at Al-Tuwaitha nuclear center in Iraq

Cited by 6 publications

References 7 publications

Measurement of Radioactive Concentrations and Determination of Isotopes Using Portable Devices for Radiochemistry Laboratories Al-Tuwaitha Nuclear Site in Iraq

Measurement of Radioactive Concentrations and Determination of Isotopes Using Portable Devices for Radiochemistry Laboratories Al-Tuwaitha Nuclear Site in Iraq

Determination of Activity Concentrations and Internal Dose Assessments in Urine from Workers in Iraqi Nuclear Research Center, Iraq

Decontamination of actual radioactive wastewater containing 137Cs using bentonite as a natural adsorbent: equilibrium, kinetics, and thermodynamic studies

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