Spark Plasma Sintering of W-UO2 Cermets

Journal Article · Fri Feb 01 00:00:00 EST 2013 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2012.08.044· OSTI ID:1056085

O'Brien, R C; Jerred, N D

About 50 vol.% 3 um depleted uranium dioxide (UO2) powder was encapsulated within a tungsten super alloy matrix produced from sub-micron tungsten powders using the Spark Plasma Sintering (SPS) process. An additive of 25 atom-percent (at.%) rhenium was included within the tungsten matrix to improve the ductility and fracture toughness of the ceramic–metallic (cermet) matrix. Cermet fabrication to 97.9% of the theoretical cermet density was achieved by sintering at 1500 degrees C with 40 MPa of applied pressure for 20 min. The results presented are from the first known trials of W–UO2 and nuclear cermet production via SPS.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: DE-AC07-05ID14517
• OSTI ID: 1056085
• Report Number(s): INL/JOU-11-24274; TRN: US1300015
• Journal Information: Journal of Nuclear Materials, Vol. 433, Issue 1 - 3; ISSN 0022-3115
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
CERMET
Fuels
Generator
Heat Source
Materials
Nuclear
Power
Radioisotope
Space
Spark Plasma Sintering
SPS
Waste