[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] BNFL Engineering, a subsidiary of British Nuclear Fuels, has developed what it believes is the world's first application of supercompaction for intermediate level radioactive waste (ILW). (author)

[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] ILW arising during the reprocessing of nuclear fuel is to be encapsulated in cement in nominal 500-litre drums. It is important that the waste package produced can be safely transported to a deep repository. Preliminary assessments of the performances of waste packages during transport for a number of the ILW streams to be generated at Sellafield have been carried out. The results show that the proposed encapsulation process produces a waste package which can be transported to an acceptable standard of safety and which does not prejudice any aspects of transport. (author)

[en] Granulates or pelletes of approx. 1 cm diameter are manufacured by means of a pelleting device and made of 1 kg portland cement with 10% bentonite and 230 g MAW simulate solution. The through-put in adjusted by selecting the diameter of the pelleting plate. (DG)

[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] This paper describes the steps involved in selecting management systems and an overall management strategy for intermediate level solid radioactive wastes. The radiological protection inputs to intermediate level waste management decisions are discussed, together with the results of preliminary radiological assessments of disposal options. Areas where further work is required are identified. (author)

[en] In order to retrieve the waste from a waste pit with small opening, the silica sands packaged in a canvas bag was used to shield the intermediate level waste (ILW). The shielding depth was calculated with QAD-CG, and the filling and retrieve of silica sands was well prepared and practiced. The dose rate at the opening was reduced from 4.28 Gy/h to 4.49 μGy/h. The waste retrieve work went on smoothly. The personnel collective dose to set and dismantle the silica sands shielding facility is 0.45 men · mSv in total. (authors)

[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] The current reference concept, i.e. the semi-hydrostatic emplacement model, for the final disposal of heat-generating high- and intermediate-level waste in deep vertical boreholes in salt provides for completely embedding each individual package in crushed salt. Load diversion by embedding in crushed salt will limit the stacking loads to the packages embedded. The Research Centre Juelich is engaged in studying theoretically as well as experimentally the applicability of this concept to a future repository. The investigations carried out to date may be summarized as follows: load diversion by embedding in crushed salt is a highly efficient tool for limiting the stacking loads in vertical repository boreholes filled with crushed salt and waste packages