Nuclear power plant containment metallic pressure boundary materials and plans for collecting and presenting their properties
Author(s) -
C.B. Oland
Publication year - 1995
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/54896
Subject(s) - containment (computer programming) , radioactive waste , oak ridge national laboratory , nuclear power , nuclear power plant , pressure vessel , corrosion , nuclear engineering , environmental science , forensic engineering , civil engineering , engineering , materials science , waste management , metallurgy , mechanical engineering , computer science , nuclear physics , physics , programming language
A program is being conducted at the Oak Ridge National Laboratory (ORNL to assist the Nuclear Regulatory Commission (NRC)) in their assessment of the effects of degradation (primarily corrosion) on the structural capacity and leaktight integrity of metal containments and steel liners of reinforced concrete structures in nuclear power plants. One of the program objectives is to characterize and quantify manifestations of corrosion on the properties of steels used to construct containment pressure boundary components. This report describes a plan for use in collecting and presenting data and information on ferrous alloys permitted for use in construction of pressure retaining components in concrete and metal containments. Discussions about various degradation mechanisms that could potentially affect the mechanical properties of these materials are also included. Conclusions and recommendations presented in this report will be used to guide the collection of data and information that will be used to prepare a material properties data base for containment steels
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