Tungsten Cladding of Tungsten-Uranium Dioxide (W-UO2) Composites by Deposition from Tungsten Hexafluoride (WF6)

Technical Report · Mon Feb 15 04:00:00 EST 1965

DOI:https://doi.org/10.2172/972754· OSTI ID:972754

Lamartine, J T; Hoppe, A W

A program is being conducted to develop a process for cladding tungsten and tungsten cermet fuels with tungsten deposited from the vapor state by the hydrogen reduction of tungsten hexafluoride. Early work was performed using recrystallized, high purity, commercial tungsten as the substrate material. Temperatures in the range 660 to 12950F (350 to 1700°C) and pressures from 10 to 350 mm Hg were investigated. Hydrogen to WF 6 ratios of 10: 1 to 150: 1 were utilized. Efforts were directed toward optimizing deposition process parameters to attain control of qualities such as coating thickness, uniformity, density, impurity content, and surface quality. Substrate penetration methods have been investigated in the interest of completely eliminating the interface between the fueled substrate and cladding. In addition, the effects of process parameters and post-cladding heat treatments on the fuel retention properties of clad composites at 4500 degrees F (2480 degrees C) in hydrogen for 2 hours have been evaluated. As a result of work performed during the first phase of the program it has been shown that the rate of deposition of tungsten from WF 6 and the uniformity of the deposit can be varied in a predictable and reproducible manner by exercising control over the temperature, pressure, and gas flow rates at which the deposits are produced. A significant result of the study is the discovery that substrate nucleation and epitaxial growth in deposits made on both unfueled tungsten and fueled substrates may be effected by pretreating the substrates in hydrogen. High temperature fuel retention testing of tungsten clad W-U02 at 45000F (2480 degrees C) in hydrogen for 2 hours has demonstrated that the vapor deposited layer effectively and consistently restricts fuel loss.

• Research Organization: National Aeronautics and Space Administration; Astronuclear Laboratory; Westinghouse Electric Corporation
• Sponsoring Organization: USDOE
• OSTI ID: 972754
• Report Number(s): WANL-PR(Z)-002; NASA CR-54426
• Country of Publication: United States
• Language: English

Related Subjects

08 HYDROGEN
CERMETS
COATINGS
DEPOSITION
GAS FLOW
HEAT TREATMENTS
HYDROGEN
NUCLEATION
RETENTION
SUBSTRATES
TESTING
THICKNESS
TUNGSTEN