[en] The handling that is given at the moment to the hospital solid waste in Costa Rica is considered inadequate, due to the lack of the personnel's of cleaning training, segregation, vehicles of transport and recipients, signaling, team of personal protection, schedule and gathering route and recycle. This situation represents a serious danger for the population's health and the since environment is exposed infectious agents toxic substances and even radioactive products that are generated in the residuals of the centers of health. In this work they intend improvements to the system of handling of solid waste of the hospital Calderon Guardia, and you evaluates each one of the points mentioned previously. A revision was made about the properties, the quality and the quantity of the produced solid waste and an I diagnose of the current situation in this center of health. The proposed improvements are based on the regional program of hospital solid waste, agreement ALA91/33 (this it was elaborated in 1997 by a cooperation initiative between the European Union and the Governments from Costa Rica, El Salvador, Guatemala, Honduras, Nicaragua and Panama) and the Norms for the Handling of dangerous Solid Waste in Establishments of Health (elaborated by the Costa Rican Box of the Public Health) their advantages and disadvantages are also exposed and he/she is carried out a comparative analysis among the handling plan proposed in these documents and the one that is used at the moment in the Calderon Guardia hospital. Some of the detected problems are: it lacks of team of personal protection, the appropriate recipients are not used, storage of waste inside the hospital, the vehicles used in the internal transport are not appropriate, bad organization of the storing center, among others

No abstract available

[en] Waste characterization activities are carried out in the liquid radioactive waste treatment process at the Radioactive Waste Technology Center which includes the characterization of initial waste, concentrate, distillate, and effluent. The process of treating liquid radioactive waste is carried out by evaporation or using ion exchange resins. Waste characterization is carried out with the aim of ensuring the suitability between the characteristics of the waste to be treated with the selected process and the suitability of the processed waste. Waste characterization is carried out from the initial waste before the evaporation and ion exchange processes, during the evaporation process the characterization is carried out to monitor the concentration of waste into concentrate and ensure that the distillate is free of radioactive contamination. In the ion exchange process, characterization is carried out to monitor the decrease in liquid waste activity and to assess the effectiveness of the resin. Characterization of the cementation concentrate or resin in the form of a concrete shell was also carried out by measuring the compressive strength and leaching rate. (author)

[en] The paper describes the problem of wastes in Lebanon and their management according to international (European and French) descriptions. It presents the situation in Lebanon including the policies taken by the ministry of environment towards the treatment of different types of wastes especially solid wastes. It is estimated that the production of wastes in Lebanon is 5854 tones per day and it is distributed as follows: Domestic wastes 3200 t/d; industrial wastes 1300 t/d; commercial wastes 1000 t/d; slaughter-houses 150 t/d; waste oils 100 t/d; hospital wastes 64 t/d; vehicle wheels 40 t/d. The annual production within regions is also presented in tables. Collection, transportation, recycling, composting and incineration of wastes are included

[en] Results are stated of investigations on process of wastes burning in device consisting of two-chamber furnace with liquid fuel and off-gas system of ''dry'' type. Solid wastes are burned in plumes of the first chamber fuel burner but smoke gases finally are burned in plumes of the second chamber. The heat source is disel oil and cobustible liquid radioactive wastes. Dependance is given of solid state phase concentration in the smoke gases on the chamber temperature. The low temperature limit of the process of burnind is 900 centigrade. Heat engineering properties of burning furnace are given and some data about ''dry'' cleaning of smoke gases are presented. Design of the device and its designed parameters are described. (I.T.)

[en] The general requirements for radioactive waste acceptance by the Laboratory of Radioactive Wastes of the Brazilian Institute of Energy and Nuclear Research - IPEN are established

[en] The future of the centralised low and intermediate level waste disposal facility at El Cabril (Cordoba) rests on its integration into the surrounding landscape. Once the disposal platforms have been filled, a final covering made up of a series of layers of soil, draining materials and low permeability materials will be put into place. Prior to drawing up the definitive project for the construction of the long-term covering layer, ENRESA decided in 2008 to initiate two scale tests to evaluate two previously defined alternatives and simultaneously acquire construction experience and obtain experimental information supporting the decisions taken in the final detailed design. The management, development and description of this R and D project constitute the subject of this article. (Author)

[en] This work has been focused on the study of the viability of barium removal, present in a waste liquid phase, by means of non-dispersive extraction (NDE) in hollow fiber modules. An organic solution based on DEPHA (Bis-2-ethylhexyl phosphate) 30% (v/v), isopropilic alcohol 30% (v/v) and kerosene is used as selective extraction medium. For the extraction process was made a contactor with five hollow microporous propilenic fibers. A solution contained 100 ppm of BaCl₂ H₂O, level concentration very equal as generated on the petroleum industrial wastes, is used as liquid phase. a efficiency of 95,25% is obtained when the NDE take place at pH = 9, and them 9 hours of process

[en] Currently, limited storage and treatment capacity exists for commercial mixed waste streams. No commercial mixed waste disposal is available, and it has been estimated that if and when commercial mixed waste disposal becomes available, the costs will be high. If high disposal fees are imposed, generators may be willing to apply extraordinary treatment or regulatory approaches to properly dispose of their mixed waste. This paper explores the feasibility of several waste management scenarios and management options. Existing data on commercially generated mixed waste streams are used to identify the realm of mixed waste known to be generated. Each waste stream is evaluated from both a regulatory and technical perspective in order to convert the waste into a strictly low-level radioactive or a hazardous waste. Alternative regulatory approaches evaluated in this paper include a delisting petition) no migration petition) and a treatability variance. For each waste stream, potentially available treatment options are identified that could lead to these variances. Waste minimization methodology and storage for decay are also considered. Economic feasibility of each option is discussed broadly. Another option for mixed waste management that is being explored is the feasibility of Department of Energy (DOE) accepting commercial mixed waste for treatment, storage, and disposal. A study has been completed that analyzes DOE treatment capacity in comparison with commercial mixed waste streams. (author)

[en] This work approaches some aspects related with definition, characteristics, process, storage and final disposal of the radioactive wastes produced by the nuclear power plants