LUBRICATION OF TITANIUM. Period Covered: March 14, 1956 to February 14, 1957
Technical Report
·
OSTI ID:4335361
Corrosion Studies. Results of an extensive investigation of chloride stress corrosion testing of type 347 stainless steel steam generator tubing are presented. Experiments to determine the effect of corrosion on type 304 stainless steel with varying carbon content in reference primary coolant water are given. Van de Graaff studies were undertaken to determine what variables are involved in the phenomenon of preferential deposition of crud on fuel element surfaces. Calculated deposited crud activity in the Shippingport Pressurized Water Reactor primary system due to corrosion of core materials is given. An investigation of corrosion and crud deposition of Zircaloy surfaces under nucleate boiling is given. Decontamination. Methods of decontamination of structural materials and surface coatings for use in nuclear installations are given. Analytical Instrumentation. The theory behind the design of a system for locating and detecting fuel element failure is presented. Materials Application. A brief summary is presented of the present status of development work intended to enable the substitution of ordinary carbon steel for stainless steel in primary and purification systems of pressurized water reactors. As a result of a fabrication development program a Zircaloy-2 tube was built to facilitate in-pile testing of reactor fuel elements. Mechanical properties of Co--Cr alloy bearing materials in compression at elevated temperatures are presented. Welding and Brazing. A standard seal weld machine is described which was designed to seal- weld all mechanisms, fuel ports, and instrument ports of a single reactor. (W.L.H.)
- Research Organization:
- Clevite Research Center, Cleveland
- NSA Number:
- NSA-12-000195
- OSTI ID:
- 4335361
- Report Number(s):
- WADC-TR-57-61(Pt.I)
- Country of Publication:
- United States
- Language:
- English
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