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[en] The guidance contained in the present document is issued by the Environment Agency, the Scottish Environment Protection Agency and the Department of the Environment for Northern Ireland. It takes account of the policy set out in Cm 2919, and is issued after consultation with Government Departments, the Health and Safety Executive and the National Radiological Protection Board, and after extensive public consultation. It focuses on issues of regulation under RSA 93 in respect of the disposal of low and intermediate level radioactive waste to specialised facilities on land and, in this regard, supersedes the guidance given in the 1984 document. Any application for authorisation of disposal of radioactive waste to such facilities will be considered on its merits, taking into account the guidance contained in this document and any representations made by statutory consultees and other respondents to the public consultation that will be undertaken at the time
[en] Low and intermediate level radioactive waste has been produced in Germany for several decades. While a part of the waste had been deposited in the Morleben repository and the Asse mine which have been operated for just a limited period of time, the major amount is conditioned and packaged in temporarily stored waste containers. Those containers are designated for final disposal in the KONRAD repository being currently under construction and expected to start operation in 2022. As a consequence, an assessment of the waste container documentation and safety is strongly needed to receive an approval for the Konrad repository. This requalification is challenging because those old containers have to meet the same safety requirements as new containers. (authors)
[en] This publication explores disposal approaches for long lived low and intermediate level radioactive waste. It provides an overview of possible disposal concepts and facilities to be considered for accepting long lived waste, advises on the key factors to be considered when selecting the appropriate disposal approach, and outlines the procedure for selecting the relevant strategy for disposal of long lived low and intermediate level waste. The information provided on these issues will be useful to decision makers, regulatory authorities, and those individuals or institutions that are interested in planning a national system for the long term management of long lived low and intermediate level waste.
[en] A brief description is given of current development work in the UK in support of the treatment and packaging of Intermediate Level Wastes (ILW) arising from the operation and decommissioning of nuclear power stations. The underlying guidelines are first identified together with a brief description of the waste types and origins. Experience with waste/cement interactions is then considered with reference to examples which have been dealt with. The overall requirements of the cement encapsulation process are then considered in the context of the required waste form properties and the reasons why some are important. This leads logically to a consideration of some of the supporting development areas where particular waste form properties are monitored. Attention is then given to the current strategy towards encapsulation plant in the UK, with reference to both fixed and mobile plant. Finally, some of the current areas of future development are discussed, either in the context of representing a preferred option or as representing a fall-back situation in case certain wastes are restricted for disposal in the future in terms of their type or quantity
[en] A subcommittee of the Radioactive Operations Committee met with the Operators of the Intermediate Level Waste Evaporator Facility on February 17, 1972, to discuss the status of the facility and its operations since the review of October 7, 1970, and reported in ORNL-CF-70-11-12. This review was made to determine the status of the ILWEF since the last review, to discuss compliance with previously recommended changes, and to review any new items of safety significance. Several recommendations were made.
[en] Bitumen is employed as an embedding matrix for low and medium level radioactive wastes. An high impermeability and a great resistance against most of chemicals are two of main bitumen properties. These characteristics of bitumen confinement properties may be modified under environmental parameters during intermediate storage or deep repository such as radiations or the presence of water. The radio-oxidation induces an increase of the quantity of leached organic matter. The evolution of the soluble organic species release seems to be linear with the irradiation dose, as soon as the dose is higher than 20 kGy, and seems to be no dependant of the dose rate. The generation of water-soluble organic complexing agents can affect the integrity of the wasteform due to an increase of the radionuclides solubility. An increase of the quantity of leached organic matter is also observed in presence of alkaline solutions. Identified molecules, by GC/MS analysis, are aromatics like naphthalene, oxidised compounds like alcohols, linear carbonyls, aromatics, glycols and nitrogen compounds. (authors)