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Journal Articles

Sintering and characterization of ZrN and (Dy,Zr)N as surrogate materials for fast reactor nitride fuel

Pukari, M.*; Takano, Masahide

Journal of Nuclear Materials, 444(1-3), p.7 - 13, 2014/01

 Times Cited Count:7 Percentile:57.39(Materials Science, Multidisciplinary)

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.

Journal Articles

Sintering and characterization of (Pu,Zr)N

Pukari, M.*; Takano, Masahide; Nishi, Tsuyoshi

Journal of Nuclear Materials, 444(1-3), p.421 - 427, 2014/01

 Times Cited Count:12 Percentile:67.72(Materials Science, Multidisciplinary)

Nitride fuel with the composition (Pu$$_{0.4}$$Zr$$_{0.6}$$)N is fabricated for studying the sinterability of nitride fuel as a function of oxygen concentration in the material. Oxygen concentration of up to 0.6 wt% evidently enhances the densification of the material. Increasing the sintering temperature from 1923 to 1973 K improves the sintered pellet densities by up to 3.8%TD. In addition, the measured thermophysical and electrical properties of (Pu$$_{0.4}$$Zr$$_{0.6}$$)N reveal that the values are close to those of PuN. Oxygen concentration of 0.34 wt% in (Pu,Zr)N is a consequence of the fabrication process, considering the relatively pure ZrN (0.03 wt% O) and PuN (0.08 wt% O) powders initially fabricated.

Journal Articles

Sinterability of ZrN and (Zr$$_{0.6}$$Dy$$_{0.4}$$)N pellets; Surrogate fuel fabrication for ELECTRA

Pukari, M.*; Takano, Masahide

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Safe Technologies and Sustainable Scenarios (FR-13) (USB Flash Drive), 8 Pages, 2013/03

Pellets of inert matrix material ZrN and surrogate nitride fuel material (Zr$$_{0.6}$$Dy$$_{0.4}$$)N are fabricated for the purpose of investigating the origin and the effect of C and O impurity concentrations. Oxygen concentrations of up to 1.5 wt% were deliberately introduced to the materials with two separate methods. The achievable green and sintered pellet densities of these materials as a function of O content, dimensional properties of the powder and sintering temperature are shown. The effect of O dissolved into the matrix vs oxide-rich phase segregation is discussed. Oxygen pickup 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.

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