Sintering and characterization of ZrN and (Dy,Zr)N as surrogate materials for fast reactor nitride fuel
Pukari, M.*; 高野 公秀
Pukari, M.*; Takano, Masahide
Pellets of inert matrix material ZrN, and surrogate nitride fuel material (Dy$$_{0.4}$$Zr$$_{0.6}$$)N, are fabricated for the purpose of investigating the origin and the effect of carbon and oxygen impurity concentrations. Oxygen concentrations of up to 1.2 wt% are deliberately introduced into the materials with two separate methods. The achievable pellet densities of these materials, as a function of O content, sintering temperature and dimensional powder properties are determined. O dissolved into (Dy,Zr)N increases the achievable densities to a larger extent than if dissolved into ZrN. The segregation of O-rich phases in ZrN indicates a low O solubility in the material. Oxygen pick-up during the fabrication of the product as well as its exposure to air is demonstrated. The quality of the materials is monitored by the systematic analysis of O, N and C contents throughout the fabrication and sintering processes, supported by XRD and SEM analyses.
使用言語 : English
掲載資料名 : Journal of Nuclear Materials
: 444
: 1-3
ページ数 : p.7 - 13
発行年月 : 2014/01
出版社名 : Elsevier
特許データ :
論文URL :
キーワード : no keyword
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 :
登録番号 : AA20121093
抄録集掲載番号 : 42000039
論文投稿番号 : 13543
Accesses  (From Jun. 2, 2014)
- Accesses
分野:Materials Science, Multidisciplinary
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