journal article·2023-05Open access

Uranium nitride stability in aqueous solutions under anoxic and oxidizing conditions – Expected behaviour under repository conditions in comparison to alternative nuclear fuel materials

Sawsan El Jamal, Yulia Mishchenko, Mats Jonsson

Abstract

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.
Source: openalex_inverted_index · Quality: baseline

Research context

OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (45)

Show source-provided references
1. Progress in nuclear energy preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR10.1016/j.pnucene.2013.11.008 ↗
2. Impact of accident-tolerant fuels and claddings on the overall fuel cycle: a preliminary systems analysis10.13182/NT14-22 ↗
3. Synthesis and sintering of UN-UO2 fuel composites10.1016/j.jnucmat.2015.06.029 ↗
4. Chemical forms of solid fission products in the irradiated uranium-plutonium mixed nitride fuel10.1016/0022-3115(94)90233-X ↗
5. Albiol · Review of Actinide Nitride Properties with Focus on Safety Aspects · 2001
6. Kinetic and microstructural studies of thermal decomposition in uranium mononitride compacts subjected to heating in high-purity helium10.1016/j.jnucmat.2016.04.018 ↗
7. Volatilization characteristics of uranium mononitride10.1016/0022-3115(69)90041-5 ↗
8. Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains10.1016/j.jnucmat.2021.153249 ↗
9. Solubility of UO2. A comparative review10.1016/0191-815X(85)90080-4 ↗
10. Development of geological disposal concepts10.1016/S1569-4860(06)09003-6 ↗
11. Studies on metal carbonate equilibria. Part 10. A solubility study of the complex formation in the Uranium(VI)-water-carbon dioxide(g) system at 25 C10.1039/DT9840002439 ↗
12. Spinks · 1990
13. The relative impact of radiolysis products in radiation induced oxidative dissolution of UO210.1016/j.jnucmat.2006.04.001 ↗
14. Long-term storage of spent nuclear fuel10.1038/nmat4226 ↗
15. Fuel corrosion processes under waste disposal conditions10.1016/S0022-3115(00)00392-5 ↗
16. Studies on metal carbonate equilibria. Part 10. A solubility study of the complex formation in the Uranium(VI)-water-carbon dioxide (g) system at 25 °C10.1039/DT9840002439 ↗
17. Effects of HCO3- on the kinetics of UO2 oxidation by H2O210.1016/j.jnucmat.2006.07.008 ↗
18. On the change in UO2 redox reactivity as a function of H2O2 exposure10.1039/C9DT04395K ↗
19. Reactivity of H2O2 towards different UO2-based materials: the relative impact of radiolysis products revisited10.1016/j.jnucmat.2011.06.003 ↗
20. Oxidation of UO2 by radiolytic oxidants10.1016/j.jnucmat.2003.07.001 ↗
21. H2O2 and radiation induced dissolution of UO2 and SIMFUEL pellets10.1016/j.jnucmat.2011.01.020 ↗
22. On the stability of uranium carbide in aqueous solution - effects of HCO3-and H2O210.1021/acsomega.1c04581 ↗
23. Radiation induced dissolution of U3Si2 - a potential accident tolerant fuel10.1016/j.jnucmat.2019.01.023 ↗
24. Kinetic study of the oxidative dissolution of UO2 in aqueous carbonate media10.1021/ie049457y ↗
25. Hydrolysis of uranium carbides between 25 and 100° I. uranium monocarbide10.1021/ic50003a047 ↗
26. Reactions of uranium carbides with aqueous sodium hydroxide solutions10.1016/0022-1902(68)80205-2 ↗
27. XPS and XRD studies of corrosion of uranium nitride by water10.1016/S0925-8388(98)00157-1 ↗
28. Kinetics of the oxidation of UN and U(CO) in carbon dioxide, steam and water at elevated temperatures10.1016/S0010-938X(66)80046-X ↗
29. Hydrolysis of uranium nitrides
30. Reactions of uranium mononitride, thorium monocarbide and uranium monocarbide with nitric acid and other aqueous reagents10.1016/0022-1902(68)80393-8 ↗
31. Hydrolysis of uranium mononitride10.1039/tf9676301286 ↗
32. Oxidation and hydrolysis kinetic studies on UN10.1016/0022-3115(91)90340-D ↗
33. Oxidation of uranium mononitride10.1016/0022-3115(75)90208-1 ↗
34. The oxidation of UC and UN powder in air10.1080/18811248.1968.9732521 ↗
35. Oxidation of uranium mononitride and uranium monocarbide10.1039/tf9666203591 ↗
36. The role of surface-bound hydroxyl radicals in the reaction between H2O2 and UO210.1080/00958972.2018.1466287 ↗
37. Impact of stoichiometry on the mechanism and kinetics of oxidative dissolution of UO2 Induced by H2 O2 and γ -irradiation10.1021/acs.jpcc.9b00862 ↗
38. Radiation induced dissolution of U 3 Si 2 - a potential accident tolerant fuel10.1016/j.jnucmat.2019.01.023 ↗
39. Manufacture of fully dense uranium nitride pellets using hydride derived powders with spark plasma sintering10.1016/j.jnucmat.2014.06.012 ↗
40. Decomposition of water and aqueous solutions under mixed fast neutron and gamma radiation10.1021/j150497a007 ↗
41. Effects of Y-radiation on ice10.1021/ja01594a004 ↗
42. Analytical use of Arsenazo III10.1016/0039-9140(61)80164-1 ↗
43. Spectrophotometric method for the determination of uranium in urine10.1021/ac00276a070 ↗
44. The structures of the carbides, nitrides and oxides of uranium10.1021/ja01181a029 ↗
45. The analysis of powder diffraction data10.1107/S0567739482000564 ↗