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• W1489346810 abstract "Abstract The primary consideration in the safety of nuclear power plants is the protection of the operators and members of the general public both during normal operation and in the unlikely event of a nuclear incident. Thus engineered safety features must be built into the plant in order that, should there be a radioactive release, no member of the public would be subjected to an unacceptable level of risk. Since worldwide there have been few reactor accidents leading to significant radiation doses to the public, the reactor designer must resort to theoretical calculations of the consequences of hypothetical releases in order to set his design criteria. In this paper a complete description is given of the methods available which can be used to study the consequences of reactor releases; the advent of modern, fast, high-capacity computers has enabled a more comprehensive approach to this problem to be made, so that the results of variations in both design features and environmental parameters are readily available. This paper considers the various stages in the pathway from irradiated nuclear fuel to man as separate modules, in each of which mathematical models are derived to represent the transfer of radioactivity. It begins with the generation of the radioactive inventories within fuel, both fission products and the build-up of transuranic elements; the release from fuel is then considered for metal and oxide fuels, following which the effects of plate-out in the reactor circuit are discussed. There is then a detailed treatment of the behaviour of the effluent in the atmosphere including effective height of release, building entrainment, meteorological dispersion, mechanisms for ground deposition and the effects of the duration of release. Having specified the radioactive environment, its interaction with man is described including exeernal exposures from γ-emitting plumes of activity and the estimation of depth doses, as well as the internal organ doses resulting from inhalation or ingestion of radioactivity. Finally, applications of the methods are described in reanalysing the 1957 Windscale accident and in the planning of procedures for reactor accident monitoring as well as in the implications of future reactor designs to assessments of accidental releases. A brief summary of the reactor siting criteria adopted in the U.K. and in the U.S.A. has also been given as a background against which to review the predictive techniques and results from the range of studies of accidents considered." @default.
• W1489346810 created "2016-06-24" @default.
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• W1489346810 date "1978-08-01" @default.
• W1489346810 modified "2023-09-24" @default.
• W1489346810 title "Radioactive Releases from Nuclear Installations: Evaluation of Accidental Atmospheric Discharges" @default.
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• W1489346810 hasPublicationYear "1978" @default.
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