[en] The social and political processes of deciding whether the technological hazards of introducing into the UK PWRs for power generation is or is not acceptable are considered with respect to; the issues involved, risk evaluation, the subjective assessment of whether the risk is socially acceptable and the implementation of the final decision. (U.K.)

[en] The article deals with the International Atomic Energy Agency (IAEA), which is situated in Vienna. The aims of the IAEA and its work are described. The safeguards system; promotional work; technical cooperation programme; and nuclear safety work concerned with basic safety standards for radiation protection; are all discussed. (U.K.)

[en] The paper examines the role of quality assurance in the nuclear fuel supply industry. Quality assurance principles; design aspects; fuel materials; cladding materials; manufacturing aspects and operations; the cost and safety implications of quality control failures; and the practice of quality assurance; are all discussed. (U.K.)

[en] The role of the present process computers in use on the Maine Yankee PWR is discussed. An ever increasing number of monitoring input points necessary for the safe and efficient operation of the plant have necessitated the ordering of four new process monitoring computers from Modcomp. Alterations to the computer room to house the new computers, the software, and the training of personnel in the use of the system are discussed. Lessons learned from the TMI accident which are relevant to the new system are examined. (U.K.)

[en] Current UK policy and practices for the management of low and intermediate activity wastes are summarised. Methods of treatment, packaging and transport are described for those wastes which are disposed of by shallow trench burial and be sea dumping. These disposal practices are described, as are the methods of storage for those wastes awaiting disposal. Current and possible future developments are briefly outlined which include improved methods of handling and the establishment of disposal routes for all intermediate activity wastes. (author)

[en] In this lecture the AGR programme is considered in respect of problems arising from the chemistry of the coolant and of the boiler feedwater under the headings: (1) Background to the choice of the AGR. (2) Main features of the AGR. (3) Choice of coolant gas. (4) Coolant chemistry. (5) Control of coolant composition. (6) Coolant strategy. (7) Sulphur in reactor gas. (8) Other minor impurities in reactor gas. (9) AGR boilers. (10) Feedwater purity. (11) Analytical methods. (12) Fuel element cooling ponds. (13) Commissioning and operation of Hinkley point 'B'. (U.K.)

[en] Having traced the development of gas cooled breeder reactors in the light of changes in the nuclear programme over the years, uranium utilisation and the overall economics of these reactors, the design of a low capital cost, large CO₂ breeder, named the ETGBR, is examined. (U.K.)

[en] A bi-dimensional finite element code for the thermal and stress analysis of ceramic pellet/metal cladding tube interactions in nuclear reactor fuel elements is described. Results obtained with the programme for a specific problem are given and show an increase of hoop stresses in the cladding tube up to 200 MPa during the postulated interaction. Thus the yield stress limit of irradiated Zircaloy, assumed to be about 520 MPa, has not been approached and the pin structure may be considered safe and reliable with given loading. (U.K.)

[en] Using the reduction of thermal neutron flux peaks within a fuel module of the original Shippingport reactor as an illustration it is shown that the principles of core design can be presented in a simple and intuitive way without the need to resort to mathematical physics. (U.K.)

[en] The paper describes the work carried out at Windscale's reprocessing site for thermal reactor fuels. Thermal reactor fuel behaviour is discussed, with reference to Magnox fuel, AGR fuel and water fuel. Fuel work that has application to more than one reactor system is mentioned. The plutonium studies on the development of the mixed plutonium/uranium oxide fuel for use in fast reactors is also considered. (U.K.)