Thermo-chemical modelling of uranium-free nitride fuels
2004 (English)In: Journal of Nuclear Science and Technology, ISSN 0022-3131, E-ISSN 1881-1248, Vol. 41, no 4, 457-465 p.Article in journal (Refereed) Published
A production process for americium-bearing, uranium-free nitride fuels was modelled using the newly developed ALCHYMY thermochemical database. The results suggested that the practical difficulties with yield and purity are of a kinetic rather than a thermodynamical nature. We predict that the immediate product of the typical decarburisation step is not methane, but hydrogen cyanide. HCN may then undergo further reactions upon cooling, explaining the difficulty in observing any carbophoric molecules in the gaseous off stream. The thermal stability of nitride fuels in different environments was also estimated. We show that sintering of nitride compounds containing americium should be performed under nitrogen atmosphere in order to the avoid the excessive losses of americium reported from sintering under inert gas. Addition of nitrogen in small amounts to fuel pin filling gas also appears to significantly improve the in-pile stability of transuranium nitride fuels.
Place, publisher, year, edition, pages
2004. Vol. 41, no 4, 457-465 p.
thermo-chemical modelling, minor actinides, uranium-free nitride fuels, carbothermic nitridation, decarburisation, thermal stability, accelerator-driven systems, carbothermic synthesis, plutonium nitride, behavior, system, matrix
IdentifiersURN: urn:nbn:se:kth:diva-23506ISI: 000222102500008ScopusID: 2-s2.0-2942755880OAI: oai:DiVA.org:kth-23506DiVA: diva2:342204
QC 20100525 QC 201110282010-08-102010-08-102016-03-16Bibliographically approved