[en] A report is given of the conference 'Gas-cooled reactors today', which was held in Bristol on 20-24 September 1982. Experience with the AGR in Britain was emphasised. Research and development work on the HTGR, particularly in Germany and the United States, was discussed. It is concluded that although the full potential of these systems has yet to be realized, their long term future remains uncertain. (U.K.)

[en] A probabilistic safety analysis or assessment (PSA) or risk analysis of a nuclear power plant is a method to assess the safety of nuclear power plants integrally. Such an analysis tests the design as well as the operational management of the plant. PSA also assesses the site of the plant with regard to the public health. An overview is given of the multi-barrier concept as applied in the Borssele pwr type reactor in the Netherlands. Special attention is paid to the use of three PSA-levels in a pwr type reactor (Borssele in the Netherlands). A level-1 analysis consists of ten specific tasks, which are briefly discussed. A level-2 analysis consists of an analysis of the physical and chemical events from the start of a nuclear degradation process to the release of nuclear products into the environment. In a level-3 analysis the consequences of the release for the public health can be determined by means of atmospheric distribution models and so-called consequence models. 5 figs

[en] Short communication

[en] Short communication

[en] Short communication

No abstract available

No abstract available

[en] Short communication

No abstract available

[en] This report presents a reload safety evaluation for Ulchin-2, Cycle 4 and demonstrates that the core being composed of various fuel types as described in the report will not adversely affect the safety of the public and the plant. All of the accidents comprising the licensing bases which could potentially be affected by the fuel reload have been reviewed for the Cycle 4 core and results are described in the report. (Author)