Articolele autorului Carmen Arsene
Link la profilul stiintific al lui Carmen Arsene

H-3 and Am-241 migration studies in experimental plots

The disposal concept proposed for the long term disposal of low and intermediate level radioactive wastes resulted from Cernavoda NPP is of surface facility with multiple barriers. The multiple barriers system designed for the Low and Intermediate Level Waste Repository - DFDSMA achieves protection in depth/profundity, through the combination of: engineered barriers, natural barriers (characteristics favoured by the natural site/location), the control

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Loss of 60 Co, 134 Cs and 137 Cs during the leaching test in the conditioned resins block

The goal of this work is the study of immobilization of spent ion exchangers resulted from the treatment of liquid radioactive wastes from Decontamination Center as a monolithic block, so that the safety of the environment be ensured, during final disposal, according to international standards all along the required time for radionuclides delay, until an acceptable level is attained. The spent resin contains a large number of radionuclides (54Mn,

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Conditioning technology for radioactive waste resulted from the treatment of liquid waste from the Romanian Nuclear Power Plant

One of the main directions from the Romanian R&D radioactive waste management program, initiated in 1992, four years before the start-up of the Cernavoda Nuclear Power Plant, is to establish the treatment and conditioning technologies for low and intermediate radioactive waste generated from operation of the plant. Researches for the treatment of the liquid radioactive wastes from the Decontamination Center have showed the ion-exchange method as

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Experimental research of 14C migration in loess and clay – distribution coefficients and retardation factors

Since 1994, the Saligny site, the potential location for low and intermediate repository in Romania, has been under physical, chemical, hydrological, mineralogical and radionuclide migration investigations. The understanding and quantification of radionuclide transport in the geological medium is of primary importance with respect to safety and environmental impact assessment for prospective waste management site. Because of its radiochemical characteristics,

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Degradation products of the ion exchangers during the bituminization process of spent resin

During the bituminization process of spent resins, because of the high temperature, a significant amount of gas is produced. Besides water vapours, it contains degradation products of resin and bitumen. The qualitative and quantitative analysis of the condensable gas mixture was made by a tandem technique, GC/MS system. All resulted compounds have been determined: dimethyl- and trimethylamine, n-paraffins (C8-C27), isoparaffins and aromatic hydrocarbons

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The pilot plant for conditioning the ion exchangers contaminated with C-14 generated by Cernavoda NPP

The research works had in view the establishing of conditioning technological process of spent ion exchangers contaminated with 14C, conceving, design and building of the pilot plant. For determination of the optimum process parameters within which the plant operates immobilization experiments of these resins were carried out. The simulated inactive wastes (A 600 and C100H ion exchangers) have been used in the bituminization experiments. The anionite

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Leaching tests of immobilized ion exchangers contaminated with C-14

For the conditioning of ion-exchangers generated from operation of Cernavoda NPP Unit 1 techniques of direct immobilization in cement, bitumen and organic polymers have been experimented. The selected process for conditioning of spent resins is their bituminization. In view of final disposal, the container that includes the waste bitumen block is cemented and confined in an other with a larger capacity. The immobilization experiments were performed

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Experimental research of H-3 migration in unsaturated soils of Saligny-site

In the gas form, tritium doesn’t present an external irradiation risk for human body. But the oxide of this element might to come into - as an insidious water component - in the metabolic circuit, quickly diffusing in the whole body, representing a long - internal irradiation source, with a high biological efectivity. The special precautions for tritium are justified for all the sectors handling tritiated water especially when considering the nuclear

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Experimental research of Am-241 migration from L/ILW in soils – transport parameters

A programme on the safety analysis linked to the geological disposal of radioactive wastes is under study at the Institute for Nuclear Research Pitesti. In relation to the migration of radionuclides in the terrestrial environment following a possible release from the repository, specific experimental studies have been developed in order to provide the necessary input data for the risk assessment models. The paper reports the results of studies performed

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