A micromechanical model for predicting hydride embrittlement in nuclear fuel cladding material

1996 ◽  
Vol 227 (3) ◽  
pp. 220-236 ◽  
Author(s):  
K.S. Chan
Keyword(s):  
Nuclear Fuel ◽  
Micromechanical Model ◽  
Fuel Cladding ◽  
Nuclear Fuel Cladding ◽  
Hydride Embrittlement ◽  
Cladding Material

scholarly journals Zr–Cu alloy filler metal for brazing SiC ceramic

RSC Advances ◽  
2018 ◽  
Vol 8 (46) ◽  
pp. 26251-26254 ◽  
Author(s):  
Bofang Zhou ◽  
Keqin Feng
Keyword(s):  
Nuclear Fuel ◽  
Filler Metal ◽  
Fuel Cladding ◽  
Cu Alloy ◽  
Sic Ceramic ◽  
Nuclear Fuel Cladding ◽  
Alloy Filler ◽  
Cladding Material

The Zr–Cu filler metal is mainly used for the joining of SiC ceramic as a nuclear fuel cladding material.

Tensile Test Techniques for a Nuclear Fuel Cladding in a Hot Cell

2007 ◽  
pp. 1561-1564
Author(s):  
Do Sik Kim ◽  
Sang Bok Ahn ◽  
Wan Ho Oh ◽  
Byung Ok Yoo ◽  
Yong Sun Choo ◽  
...  
Keyword(s):  
Tensile Test ◽  
Nuclear Fuel ◽  
Fuel Cladding ◽  
Nuclear Fuel Cladding
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