Spark Plasma Sintering of W-UO2 cermets

R. C. O'Brien; N. D. Jerred; Robert O'Brien

doi:10.1016/j.jnucmat.2012.08.044

Spark Plasma Sintering of W-UO₂ cermets

R. C. O'Brien
, N. D. Jerred
, Robert O'Brien

Research output: Contribution to journal › Article › peer-review

51 Scopus citations

Abstract

About 50 vol.% 3 μm 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 °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.

Original language	English
Pages (from-to)	50-54
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	433
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2012.08.044
State	Published - 2013

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10.1016/j.jnucmat.2012.08.044

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title = "Spark Plasma Sintering of W-UO2 cermets",

abstract = "About 50 vol.\% 3 μm 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 °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.",

author = "O'Brien, \{R. C.\} and Jerred, \{N. D.\} and Robert O'Brien",

year = "2013",

doi = "10.1016/j.jnucmat.2012.08.044",

language = "English",

volume = "433",

pages = "50--54",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

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TY - JOUR

T1 - Spark Plasma Sintering of W-UO2 cermets

AU - O'Brien, R. C.

AU - Jerred, N. D.

AU - O'Brien, Robert

PY - 2013

Y1 - 2013

N2 - About 50 vol.% 3 μm 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 °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.

AB - About 50 vol.% 3 μm 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 °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.

UR - https://www.scopus.com/pages/publications/84867753128

U2 - 10.1016/j.jnucmat.2012.08.044

DO - 10.1016/j.jnucmat.2012.08.044

M3 - Article

AN - SCOPUS:84867753128

SN - 0022-3115

VL - 433

SP - 50

EP - 54

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

ER -

Spark Plasma Sintering of W-UO₂ cermets

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