scholarly journals Treatment of Radioactive Liquid Waste Using Bentonite

2021 ◽  
pp. 871-877
Author(s):  
Aamir Abdullah Mohammed ◽  
Hayder S. Hussain ◽  
Salam K. Al-Nasri
Keyword(s):  
Ion Exchange ◽  
Removal Efficiency ◽  
Liquid Waste ◽  
Radioactive Cesium ◽  
Radioactive Liquid Waste ◽  
Experimental Conditions ◽  
Exchange Method ◽  
Cesium 137 ◽  
Ion Exchange Method ◽  
Langmuir And Freundlich Models

Radioactive liquid waste contaminated with cesium-137 found in the radiochemistry laboratories at Tuwaitha site, south of Baghdad, was treated in this work. Bentonite was used as a sorbent material for the removal of radioactive cesium-137 from liquid waste by ion exchange method. The results indicated that the best removal efficiency obtained was 95.13% with experimental conditions of 2 h mixture time, 0.04 g sorbent mass, and pH=10 for the radioactive liquid. It was found that the experimental results match well with Langmuir and Freundlich models, with better matching with the latter.

Removal of radioactive cesium from liquid waste by zeolite

2021 ◽  
Vol 2 (2) ◽  
pp. 39-47
Author(s):  
Aamir Abdullah Mohammed ◽  
Hayder Saleem Hussein ◽  
Salam Khudhair Abdullah
Keyword(s):  
Removal Efficiency ◽  
Langmuir Isotherm ◽  
Room Temperature ◽  
Mixing Time ◽  
Liquid Waste ◽  
Langmuir Model ◽  
Isotherm Models ◽  
Radioactive Cesium ◽  
Freundlich Model ◽  
Cesium 137

A radioactive fluid waste polluted with cesium-137 from Al-Tuwaitha site -south of Baghdad-Iraq is used in this paper. Commercial zeolite is used as a sorbent material in the present work for the removal of radioactive cesium-137. The removal efficiency for radioactive liquid was 96.43 % with 2 h mixing time, 0.04 g sorbent mass and pH=6.8 and at room temperature. The Freundlich and Langmuir isotherm models were found to represent the experimental results well and these results are more consistent with Freundlich model than Langmuir model.

scholarly journals Total Mineralization of Malachite Green Dye by Advanced Oxidation Processes

2018 ◽  
Vol 26 (2) ◽  
pp. 263-280
Author(s):  
Diana Carmen Mirila ◽  
Mădălina-Ștefania Pîrvan ◽  
Nicoleta Platon ◽  
Ana-Maria Georgescu ◽  
Valentin Zichil ◽  
...  
Keyword(s):  
Ion Exchange ◽  
Malachite Green ◽  
Textile Industry ◽  
Advanced Oxidation Processes ◽  
Experimental Conditions ◽  
Exchange Method ◽  
Oxidation Processes ◽  
Malachite Green Dye ◽  
Ozonation Time ◽  
Ion Exchange Method

Abstract In this work, the advanced decomposition of organic dyestuffs used in food and textile industry, such as Malachite Green (MG), was investigated in the presence of a cationic catalyst montmorillonite (P1-PILCs) prepared by ion-exchange method. The obtained material was characterized by BET, FTIR and XRD. The effects of different variables such as: catalyst dose, catalyst/ozone dose, ozonation time and the pH on the mineralization of the synthetic dye were studied and optimal experimental conditions were ascertained. Compared with simple ozonation, the introduction of the catalyst greatly reduces the duration of the process to reach over 95% yield from 110 minutes to some seconds.

scholarly journals Cs-137 AND Co-60 CONCENTRATION REMOVAL ON RADIOACTIVE LIQUID WASTE BY ION EXCHANGE AND COAGULATION-FLOCCULATION METHOD

2017 ◽  
Vol 1 (1) ◽  
pp. 1
Author(s):  
Pinky Septria Adella ◽  
Asih Wijayanti ◽  
Dwi Indrawati ◽  
Sugeng Purnomo
Keyword(s):  
Ion Exchange ◽  
Batch Reactor ◽  
Liquid Waste ◽  
Ion Exchanger ◽  
Toxic Waste ◽  
Continuous Reactor ◽  
Radioactive Liquid Waste ◽  
Exchange Method ◽  
Jar Test ◽  
The Government

Radioactive liquid waste is a hazardous and toxic waste which comes from nuclear research laboratory. This waste may cause explosion when treated with evaporator. <strong>Aim:</strong> This research was intended to reduce and determine the best removal method of Cs-137 and Co-60 from radioactive liquid waste. <strong>Methodology and Result</strong>: Methods used in this research are ion exchange and coagulation-flocculation method. In ion exchange method used two types of reactor that is continuous reactor and batch reactor with variables of debit, material type, mesh size and mass of material, while in coagulation-flocculation method used jar test with ferro sulfate coagulant dose variables. Continuous reactor consisting of separating funnel and chromatography column with a diameter of 4 cm and height 60 cm, whereas in batch reactor used jar test stirrer. The application of radioactive liquid waste treatment is done using selected method, with the start condition for Cs-137 of 3 x 10-5 mCi/L and for Co-60 of 4.8 x 10-6 mCi/L. Application of Ion Exchanger with Continuous Reactor Speed 60 mL/10 sec and Coagulation-Flocculation with dose of 100 mmol/L in pH 8 effluent result the value for Cs-137 and Co-60 that undetected or very little, below 10-6 mCi/L. <strong>Conclusion, significance and impact study:</strong> The conclusion of this study is suitable with the Government Regulation Number 10 of 1997 about nuclear power, the limit of quality standard for Cs-137 and Co-60 is below 10-6 mCi/L. So the appropriate method to treat of Cs-137 and Co-60 are Ion Exchanger with Continuous Reactor Speed 60 mL/10 sec and Coagulation-Flocculation with dose of 100 mmol/L in pH 8.

Radiation Effects on Hollandite Ceramics developed for Radioactive Cesium Immobilization

2003 ◽  
Vol 792 ◽  
Author(s):  
V. Aubin ◽  
D. Caurant ◽  
D. Gourier ◽  
N. Baffier ◽  
S. Esnouf ◽  
...  
Keyword(s):  
Radiation Effects ◽  
Liquid Waste ◽  
Fission Products ◽  
Radioactive Cesium ◽  
Radioactive Liquid Waste ◽  
Epr Spectrum ◽  
Paramagnetic Resonance ◽  
Γ Radiation ◽  
The Stability ◽  
High Level

ABSTRACTProgress on separating the long-lived fission products from the high level radioactive liquid waste (HLW) has led to the development of specific host matrices, notably for the immobilization of cesium. Hollandite (nominally BaAl2Ti6O16), one of the main phases constituting Synroc, receives renewed interest as specific Cs-host wasteform. The radioactive cesium isotopes consist of short-lived Cs and Cs of high activities and Cs with long lifetime, all decaying according to Cs+→Ba2++e- (β) + γ. Therefore, Cs-host forms must be both heat and (β,γ)-radiation resistant. The purpose of this study is to estimate the stability of single phase hollandite under external β and γ radiation, simulating the decay of Cs. A hollandite ceramic of simple composition (Ba1.16Al2.32Ti5.68O16) was essentially irradiated by 1 and 2.5 MeV electrons with different fluences to simulate the β particles emitted by cesium. The generation of point defects was then followed by Electron Paramagnetic Resonance (EPR). All these electron irradiations generated defects of the same nature (oxygen centers and Ti3+ ions) but in different proportions varying with electron energy and fluence. The annealing of irradiated samples lead to the disappearance of the latter defects but gave rise to two other types of defects (aggregates of light elements and titanyl ions). It is necessary to heat at relatively high temperature (T=800°C) to recover an EPR spectrum similar to that of the pristine material. The stability of hollandite phase under radioactive cesium irradiation during the waste storage is discussed.

A highly efficient Fe-Ni-S/NF hybrid electrode for promoting oxygen evolution performance

2021 ◽  
Author(s):  
YuYun Chen ◽  
Yang Xu ◽  
Shuai Niu ◽  
Jun Yan ◽  
Ye-Yu Wu ◽  
...  
Keyword(s):  
Ion Exchange ◽  
Oxygen Evolution ◽  
Hierarchical Structure ◽  
Alkaline Solution ◽  
Exchange Method ◽  
Highly Efficient ◽  
Ion Exchange Method

In this study, a Fe-Ni-S/NF hybrid electrode with hierarchical structure was fabricated via a simple hydrothermal and ion exchange method, which exhibits remarkable OER performance in alkaline solution with an...

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