Sintering and characterization of ZrN and (Dy,Zr)N as surrogate materials for fast reactor nitride fuel
2014 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 444, no 1-3, 7-13 p.Article in journal (Refereed) Published
Pellets of inert matrix material ZrN, and surrogate nitride fuel material (Dy0.4Zr0.6)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.
Place, publisher, year, edition, pages
2014. Vol. 444, no 1-3, 7-13 p.
Effect of carbons, Oxygen concentrations, Oxygen impurity, Powder properties, Sintering process, Sintering temperatures, Surrogate materials, Systematic analysis
IdentifiersURN: urn:nbn:se:kth:diva-123530DOI: 10.1016/j.jnucmat.2013.09.001ISI: 000329888100002ScopusID: 2-s2.0-84885090542OAI: oai:DiVA.org:kth-123530DiVA: diva2:627110
QC 20140214. Updated from accepted to published.2013-06-112013-06-112014-02-14Bibliographically approved