A SURVEY OF 21 REACTOR VESSELS IN LIGHT OF THE ANTICIPATED EFFECTS OF NEUTRON IRRADIATION ON THE BRITTLE-RUPTURE PROPERTIES OF MATERIALS OF CONSTRUCTION

摘要

I. Scope of the ProblemnII. Information Now Available on the Bribrittlament ProblemnIII. The Brittle-Ductile Temperature as Danger IndicationnIV. Teste for Ascertaining the Brittle-Ductile TemperaturenV. Neutron Flux MeasurementsnVI. Surveillance and Monitoring of Reactor VesselsnVII. Effect of Temperature on thenMechanical Properties of MetalsnVIII. Status of a Selected Number of Reactor Vessels