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Nitride fuel for Gen IV nuclear power systems
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0001-6818-5724
2018 (English)In: Journal of Radioanalytical and Nuclear Chemistry, ISSN 0236-5731, E-ISSN 1588-2780, Vol. 318, p. 1713-1725Article in journal (Refereed) Published
Abstract [en]

Nuclear energy has been a part of the energy mix in many countries for decades. Today in principle all power producing reactors use the same techniqe. Either PWR or BWR fuelled with oxide fuels. This choice of fuel is not self evident and today there are suggestions to change to fuels which may be safer and more economical and also used in e.g. Gen IV nuclear power systems. One such fuel type is the nitrides. The nitrides have a better thermal conductivity than the oxides and a similar melting point and are thus have larger safety margins to melting during operation. In addition they are between 30 and 40% more dense with respect to fissile material. Drawbacks include instability with respect to water and a sometimes complicated fabrication route. The former is not really an issue with Gen IV systems but for use in the present fleet. In this paper we discuss both production and recycling potential of nitride fuels.

Place, publisher, year, edition, pages
2018. Vol. 318, p. 1713-1725
Keywords [en]
Nuclear fuel; Nitride nuclear fuels; Gen IV; Production of nitrides; Nuclear fuel recycling; Dissolution of nitrides
National Category
Engineering and Technology
Research subject
Energy Technology
Identifiers
URN: urn:nbn:se:kth:diva-249089DOI: 10.1007/s10967-018-6316-0ISI: 000451746300022Scopus ID: 2-s2.0-85056322500OAI: oai:DiVA.org:kth-249089DiVA, id: diva2:1303795
Note

QC 20190514

Available from: 2019-04-10 Created: 2019-04-10 Last updated: 2019-05-14Bibliographically approved

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Ribeiro Costa, DiogoJolkkonen, Mikael
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