CORROSION OF REACTOR STRUCTURAL MATERIALS IN HIGH-TEMPERATURE WATER. II. STATIC CORROSION BEHAVIOR AT 600 TO 680 DEG F. CORROSION OF REACTOR STRUCTURAL MATERIALS IN HIGH-TEMPERATURE WATER. II. STATIC CORROSION BEHAVIOR AT 600 TO 680 DEG F.
Data source
Japan Atomic Energy Agency's Library Catalog
A search system for the collections of the Japan Atomic Energy Agency central library. Books, reports, meeting materials, magazines and dockets collected by the library are searchable.
Last updated
August 22, 2022