Experimental Study of Thermochemical Treatment of Spent Ion- Exchange Resins (original) (raw)
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ICONE19-43160 Development of Spent Ion Exchange Resin Processing in Nuclear Power Stations
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Commercial operation of the Tsuruga nuclear power station Unit 1, owned by the Japan Atomic Power Company (JAPC), will be terminated in 2016. For safe decommissioning of the station, technologies for processing stored radioactive wastes such as spent Ion EXchange resin (IEX) and Filter Sludge (FS) have been jointly developed by JAPC and JGC Corporation. The Wet-Oxidation process (WetOx) was applied for decomposition of the spent IEX and FS, and Super Cement (SC) solidification was chosen for immobilization of the WetOx residue. Pilot scale tests for the WetOx treatment have been successfully conducted with simulated wastes. The WetOx residue is a concentrate with Suspended Solid (SS) and sodium sulfate, and was solidified by SC in lab scale cementation apparatus. The compressive strength of the solidified waste was confirmed to meet the desired level for radioactive waste disposal.
Promising Methods of Spent Ion-Exchange Resins Treatment
International Journal of Energy for a Clean Environment, 2012
The article is devoted to the analysis of the modern state of the spent ion-exchange resins (SIER) treatment problem at nuclear power plants where regeneration of resins is not provided. The importance of ion-exchange processes for nuclear-power engineering is determined and the main characteristics of spent resins are given. Technologies suggested for SIER processing and potentially suitable for this purpose are considered including conventional techniques (combustion) and advanced technologies (plasma). The most significant limitations of the SIER treatment methods are accentuated. Special emphasis is placed on the decontamination as the most advisable and prospective treatment method of SIER.
Treatment and Conditioning of Spent Ion Exchange Resin from Nuclear Power Plant
There are a number of liquid processes and waste streams at nuclear facilities (i.e. nuclear power plants, fuel reprocessing plants, nuclear research centers, etc.) that require treatment for process chemistry control reasons and/or the removal of radioactive contaminants. These processes may be for reactor primary coolants, the cleanup of spent fuel pools, liquid radioactive waste management systems, etc. One of the most common treatment methods for such aqueous streams is the use of ion exchange, which is a well developed technique that has been employed for many years in both the nuclear industry and in other industries. Nuclear power plant process water systems have typically used organic ion exchange resins to control system chemistry to minimize corrosion or the degradation of system components and to remove radioactive contaminants. Organic resins are also used in a number of chemical decontamination or cleaning processes for the regeneration of process water by reagents and ...
Immobilization of Spent Ion Exchange Resin Arising From Nuclear Power Plants: An Introduction
J. Pakistani Mater. Sci, 2009
Ion exchange resins are used for purification of radioactive waste waters in the nuclear industry. The process involves removal of radioactive nuclides and other hazardous contaminants that could potentially harm the equipment or corrode reactor fuel rods. These resins have to be replaced periodically with clean ones to continue the purification process and dispose of the spent resins. Disposal often becomes uneconomic because of the large volume of the resin produced and the relatively few technologies capable of economically stabilizing this waste. Various methods to treat liquid radioactive waste in the reactor fuel pond using ion exchange resins have been reviewed in this paper. The potential of verification to immobilize and contain the spent ion exchange resin for long term disposal using novel borosilicate glass has been discussed.
IOP Conference Series: Materials Science and Engineering
The filtration of contaminated aqueous waste streams from nuclear applications produces spent ion exchange resins (IER) which can be classified either as low level Waste (LLW) or as intermediate level Waste (ILW). For the purpose of the work conducted in the framework of the European THERAMIN project, studies considered spent IER waste form to be routed to the French deep geological disposal facility in the Callovo-Oxfordian formation (Cigéo). This form of waste is known to release hydrogen by radiolysis degradation, reactive species and complexing compounds. Today, for disposability in Cigéo, direct cementation of IER is the main immobilization process. This work aims to evaluate the application of the incineration-vitrification with plasma process, SHIVA, on a mixture of zeolites, diatoms, and spent IER in regards to the reference immobilization process by cementation. Production of an alumina-borosilicate type glass using SHIVA incineration-vitrification process was considered in order to examine the impact of this process for managing the specificities of this IER waste form with the additional advantage of minimizing the disposal volume. The potential benefits that thermal treatment can provide in the context of Cigéo for such spent IER waste form are evaluated based on the physical characterizations and leaching experiments carried out by CEA on the resulting vitrified product. The influence of thermal treatment on several characteristics in line with a generic list of Waste Acceptance Criteria (WAC) defined within the THERAMIN project have been qualitatively evaluated considering their potential influences on operational and long-term safety.
Integrated S ystem for Spent Ion Exchange Resin Processing in Nuclear Power Stations - 11164
2011
The Tsuruga nuclear power station Unit 1 owned by the Japan Atomic Power Company (JAPC) will terminate its commercial operation in 2016. For a safe decommissioning of the station, JAPC and JGC Corporation have investigated the processing of stored radioactive wastes such as spent ion exchange resin (IEX) and filter sludge (FS). A unique wet-oxidation process operating at 100 C under atmospheric pressure will be applied for decomposing organic substances in the waste. The treated waste containing radioactive species will undergo cementation using our Super Cement (SC) solidification process. For the treatment of high activity waste, the combined process of wet oxidation and SC solidification provides advantages over conventional incineration and direct solidification methods; for example, it can be operated environmentally safely under milder operating conditions with simple equipment and has the capability to reduce the volume of the waste material. It is expected that the combined...
Nuclear Technology, 2010
Incineration of spent ion exchange resin was simulated using the ChemSheet chemical calculation program. The simulation of the incineration was modeled for typical spent resin produced by pressurized water reactors (PWRs) and boiling water reactors (BWRs) in Finland. The objective of the study was to find the volume and mass reduction and the chemical compounds formed during incineration. The simulation showed that active elements did not play any role in incineration owing to small amount of Cs, Co, etc. The ash contained metal oxidesmainly hematite, iron oxide Fe 2 O 3. Other products of the incineration were water, carbon dioxide, sulfuric acid, and nitrogen oxides. The volume reductions 1/100 and 1/14 of the spent resin were obtained for PWRs and BWRs, respectively. The annual ash production from incineration was calculated to be 408 kg and 746 kg for the currently operating Finnish PWR and BWR plants in Loviisa and Olkiluoto, respectively.
Pyrolysis of Spent Ion Exchange Resins - 12210
2012
Organic ion exchangers (IEX) play a major and increasing role in the reactor coolant and other water purification processes. During their operation time they receive significant amounts of radioactivity, making their disposal, together with their organic nature, as medium active waste challenging. Processes applied so far do not eliminate the organic matter, which is unwanted in disposal facilities, or, if high temperatures are applied, raise problems with volatile radionuclides. NUKEM Technologies offers their well introduces process for the destruction of spent solvent (TBP), the pebble bed pyrolysis, now for the treatment of spent IEX (and other problematic waste), with the following benefits: the pyrolysis product is free of organic matter, and the operation temperature with approx. 500 deg. C keeps Cs radionuclides completely in the solid residue. (authors)
Advances in cement solidification technology for waste radioactive ion exchange resins: A review
Journal of Hazardous Materials, 2006
Treatment and disposal of waste radioactive ion exchange resins is one of the most urgent problems for nuclear industries in China. Cement solidification technology has many advantages, such as requiring simple equipment, easy scaling-up, low working temperature, no trouble of gas cleaning and low cost. It is a suitable technology for treatment of waste radioactive resins, and has been widely used. The new developments and theoretical basis of cement solidification of radioactive resins were introduced in this paper. The cement solidification technology suitable for China and the questions needed to solve were also discussed.
Incineration of Wet Ion Exchange Resins Mixed with Metal Fuel
wmsym.org, 1999
A technology of thermochemical treatment of wet ion exchange resins (IER) mixed with powder metal fuel (PMF) has been developed. Metal powder (Mg, Ca, Al, etc.) included in PMF reacts with moisture generating enough heat to break down IER. To burnout the products of IER decomposition and hydrogen resulting from the reaction of the metal with the moisture, the air is injected into the combustion chamber. A pilot plant has been designed and constructed. Results of the investigation have shown a high efficiency of the technology developed. Slags remained in the combustion chamber confine radionuclides in the fixed form in amounts of 90 % or more of Cs-137 and up to 95 % of Sr-90 and Co-60.