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Uranium nitride stability in aqueous solutions under anoxic and oxidizing conditions – Expected behaviour under repository conditions in comparison to alternative nuclear fuel materials
KTH, School of Engineering Sciences in Chemistry, Biotechnology and Health (CBH), Chemistry, Applied Physical Chemistry. aSchool of Engineering Sciences in Chemistry, Biotechnology and Health, Department of Chemistry, KTH Royal Institute of Technology, SE-100 44, Stockholm, Sweden.ORCID iD: 0000-0001-8553-1908
KTH, School of Industrial Engineering and Management (ITM), Materials Science and Engineering, Structures.ORCID iD: 0000-0002-8780-3695
KTH, School of Engineering Sciences in Chemistry, Biotechnology and Health (CBH), Chemistry, Applied Physical Chemistry.ORCID iD: 0000-0003-0663-0751
2023 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 578, article id 154334Article in journal (Refereed) Published
Abstract [en]

Uranium nitride (UN) has good thermo-physical properties which makes it a promising fuel candidate for generation IV nuclear reactors. In addition to its performance as a nuclear fuel, it is important to elucidate every novel fuel material in terms of its stability in aqueous environments. This can be highly relevant under certain accident scenarios and also for the safety assessment of geological repositories for used nuclear fuel. The fuel matrix contains the fission products and heavier actinides formed under normal reactor operation. Upon dissolution of the fuel matrix, these highly radiotoxic constitiuents can be released. In this work UN has been studied under aqueous conditions similar to a geological repository for spent nuclear fuel. For UN, direct hydrolysis as well as oxidative dissolution induced by water radiolysis can lead to degradation of the fuel matrix. The latter process leads to formation of oxidative radiolysis products of which H2O2 has been shown to be the most important oxidant for other fuel materials. The experiments show that hydrolysis of UN in aqueous solutions and exposure to solutions containing H2O2 resulted in matrix dissolution. However, this oxidative dissolution induced by H2O2 is more prominent than hydrolysis in water with or without added HCO3−. The dissolution of UN was compared with other nuclear fuel materials (UC, UO2 and U3Si2) under the same conditions. The results show that UN is the second most reactive fuel material towards H2O2. However, the so-called dissolution yield is the lowest for UN. The rationale for the observed differences in reactivity are discussed.

Place, publisher, year, edition, pages
Elsevier B.V. , 2023. Vol. 578, article id 154334
Keywords [en]
Different uranium based materials, H O 2 2, Oxidative dissolution, Stability
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-330961DOI: 10.1016/j.jnucmat.2023.154334ISI: 000949014600001Scopus ID: 2-s2.0-85148685265OAI: oai:DiVA.org:kth-330961DiVA, id: diva2:1779646
Note

QC 20230704

Available from: 2023-07-04 Created: 2023-07-04 Last updated: 2023-07-04Bibliographically approved

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El Jamal, SawsanMishchenko, YuliaJonsson, Mats

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