[en] Letter to the editor

No abstract available

No abstract available

[en] Growing world interest in nuclear energy will involve increased demand for uranium which may be in short supply by 1980s, Therefore, the fast breeder reactor, which produces more fuel than it consumes, will play an important role. In Britain, work on fast reactors started in the early 1950s, while an experimental version is in operation since 1959. A 250 megawatt (electrical) prototype is now completing a comprehensive test and commissioning programme. Design specifications for the PFR are given. (S.K.K.)

[en] A brief description of the Establishment, including DFR, PFR, fuels, materials testing, waste management, health and safety and future prospects is given. (UK)

[en] Brief item

[en] Britain's fast reactor programme is reviewed. The experience gained with te DFR and PFR reactors is examined and the applications to the proposed CDFR (Commercial Demonstration Fast Reactor) discussed. (U.K.)

[en] Automatic translation: Fuel element graphites based on gilsonite coke were irradiated in the DFR Dounreay in the temperature range from 600 to 1400°C up to a maximum dose of 4.5 * 10²¹ cm^-2 (EDN). The irradiation setup and irradiation process are briefly described. The radiation-induced dimensional changes and physical property changes are summarized and evaluated in tabular form.

No abstract available

[en] The Dounreay site is situated on the north coast of Scotland, mainland United Kingdom, and since the 1950s it has been instrumental in fast breeder research and fuel reprocessing plant development. The work programme on the site has changed, and is now one of safe decommissioning and site restoration. Previous papers have discussed and reviewed progress during the very early stages of the decommissioning programme and this paper provides an update on the work programme from a primarily radiation protection perspective. This paper discusses progress in decommissioning the Dounreay site and the adoption of 'tried and tested', as well as innovative techniques to achieve this decommissioning safely. This includes detailed discussion of the radiation protection aspects of decommissioning, and the consideration and implementation of various radiological protection controls within varying decommissioning environments, such as: a) Remote operations; b) Robotics; c) Shielding; d) Remote readout dosimetry (during personnel entry into elevated dose rate areas). The change from an operational to a decommissioning work programme at Dounreay, created a requirement to modify the type and variety of radiological personal protective equipment (PPE) available. The selection of appropriate PPE, utilised following exhaustion of the hierarchy of controls, to remove the residual radiological risk to personnel is discussed within the paper. The benefit of developing this PPE, as well as other controls, in collaboration with the operatives performing the work, is clearly obvious. The paper concludes with a review of the relative merits and success of the decommissioning techniques that have been adopted, from a radiological protection perspective, together with a summary of lessons learnt. (author)