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- W172004385 abstract "A review is presented of the various aspects of reactor materials important to the design of the Calder Hall type graphite moderated reactor and of the Windscale Advanced Gas-cooled Reactor. Some factors leading to the selection of CO/sub 2/ as a coolant are described, and its specification is given. The principal problems associated with the use of a graphite moderator are outlined. Following discussion of the influence of design on the initial requirements of density, strength, and permeability to gases, the effects of irradiation are discussed. Neutron irradiation causes accumulation of stored energy in the graphite which could be hazardous if released at an excessive rate during transient conditions. However, selection of a minimum graphite operating temperature in relation to the flux rating of a particular design ensures that the maximum possible energy release rate will not exceed a critical value during the lifetime of the reactor. Neutron bombardment also causes dimensional changes in the graphite, and curves showing the expected trends of behavior are presented. Design measures to ensure that the graphite structure will continue to behave satisfactorily in the presence of gross dimensional changes are described, and mention is made of the problems arising from differential growth effects.more » While thermal reaction of graphite with CO/sub 2/ is not a problem below 600 deg C, attack of the graphite can occur in the reactor because of radiolytic decomposition of CO/sub 2/, the weight loss increasing with higher neutron and gamma flux ratings and increased gas pressures. In the A.G.R., controlled additions of CO will be necessary to reduce the rate of attack. Factors influencing the continual safe working of a steel pressure vessel are outlined. Particular attention is given to the safeguards used to avoid brittle fracture and to the effects of irradiation. Data on high temperature properties and fatigue behavior are summarized. The oxidation behavior of various pressure circuit materials in CO/sub 2/ is described, the data indicating that these materials will be satisfactory at the conditions of service in the Windscale A.G.R. Finally, a summary is given of the measures taken in the operating reactors to monitor for changes in properties of the steel and graphite. (auth)« less" @default.
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- W172004385 date "1962-01-01" @default.
- W172004385 modified "2023-09-26" @default.
- W172004385 title "REVIEW OF MATERIALS FOR GAS-COOLED REACTORS" @default.
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