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D.B. Glanton
D.B. Glanton
Ceramic
Nuclear fuel cycle
Oak Ridge National Laboratory
Welding
Alloy
1
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4
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Tensile and Creep-Rupture Evaluation of a New Heat of Haynes Alloy 25
2007
J.P. Shingledecker
D.B. Glanton
R. L. Martin
B. L. Sparks
R. W. Swindeman
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