Radiation induced dissolution of U3Si2 - A potential accident tolerant fuel

Maier, Annika Carolin; Benarosch, Anna; Jamal, Ghada El; Jönsson, Mats

doi:10.1016/j.jnucmat.2019.01.023

Cited by 3 publications

(6 citation statements)

References 24 publications

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“…The H 2 O 2 concentration in the same system decreases quite slowly after the initial rapid decrease. The evolution of the H 2 O 2 and uranium concentrations in the HCO 3 – deficient system can probably be attributed to the formation of a secondary phase, probably studtite [UO 2 (O 2 ) (H 2 O) 4 ]. − The same reaction dynamics, that is, that the uranium concentration initially increases rapidly and thereafter slowly decreases has been observed for UO 2 as well in solutions without added HCO 3 – . The slow precipitation of studtite from fairly colloidally stable studtite particles makes it difficult to experimentally determine the concentrations of free H 2 O 2 and U(VI) in these solutions…”

Section: Resultsmentioning

confidence: 70%

“…38 U 3 Si 2 , in turn, was found to be around one order of magnitude more reactive than UO 2 . 38 In other words, the reactivity of UC toward H 2 O 2 is higher than that of UO 2 and U 3 Si 2 . For UC, it should be kept in mind that extensive hydrolysis would result in formation of a UO 2 surface and the reactivity would then not be expected to differ from that of UO 2 .…”

Section: ■ Results and Discussionmentioning

confidence: 90%

“…30%) than the reactivity of U 3 Si 2 , an accident tolerant fuel candidate that was recently studied . U 3 Si 2 , in turn, was found to be around one order of magnitude more reactive than UO 2 . In other words, the reactivity of UC toward H 2 O 2 is higher than that of UO 2 and U 3 Si 2 .…”

Section: Resultsmentioning

confidence: 90%

“…38 This can partly be attributed to the fact that oxidative dissolution of UC is not necessarily a strict two-electron process which was also demonstrated for U 3 Si 2 , where H 2 O 2 is also consumed by oxidizing Si. 38 Hence, H 2 O 2 may also be consumed in oxidation of carbon.…”

Section: ■ Results and Discussionmentioning

confidence: 90%

“…The reactivity of UC toward H 2 O 2 is higher (by ca. 30%) than the reactivity of U 3 Si 2 , an accident tolerant fuel candidate that was recently studied . U 3 Si 2 , in turn, was found to be around one order of magnitude more reactive than UO 2 .…”

Section: Resultsmentioning

confidence: 91%

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On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO₃^– and H₂O₂

2021

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Uranium carbide (UC) is a candidate fuel material for future Generation IV nuclear reactors. As part of a general safety assessment, it is important to understand how fuel materials behave in aqueous systems in the event of accidents or upon complete barrier failure in a geological repository for spent nuclear fuel. As irradiated nuclear fuel is radioactive, it is important to consider radiolysis of water as a process where strongly oxidizing species can be produced. These species may display high reactivity toward the fuel itself and thereby influence its integrity. The most important radiolytic oxidant under repository conditions has been shown to be H 2 O 2 . In this work, we have studied the dissolution of uranium upon exposure of UC powder to aqueous solutions containing HCO 3 − and H 2 O 2 , separately and in combination. The experiments show that UC dissolves quite readily in aqueous solution containing 10 mM HCO 3 − and that the presence of H 2 O 2 increases the dissolution further. UC also dissolves in pure water after the addition of H 2 O 2 , but more slowly than in solutions containing both HCO 3 − and H 2 O 2 . The experimental results are discussed in view of possible mechanisms.

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Section: Resultsmentioning

confidence: 70%

Section: ■ Results and Discussionmentioning

confidence: 90%

Section: Resultsmentioning

confidence: 90%

Section: ■ Results and Discussionmentioning

confidence: 90%

Section: Resultsmentioning

confidence: 91%

See 3 more Smart Citations

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO₃^– and H₂O₂

2021

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Thermal and mechanical properties of U3Si2: A combined ab-initio and molecular dynamics study

Kaloni

Torres

2020

Journal of Nuclear Materials

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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

Jamal

Mishchenko

Jönsson

2023

Journal of Nuclear Materials

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Radiation induced dissolution of U3Si2 - A potential accident tolerant fuel

Cited by 3 publications

References 24 publications

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO₃^– and H₂O₂

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO₃^– and H₂O₂

Thermal and mechanical properties of U3Si2: A combined ab-initio and molecular dynamics study

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

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Radiation induced dissolution of U3Si2 - A potential accident tolerant fuel

Cited by 3 publications

References 24 publications

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO3– and H2O2

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO3– and H2O2

Thermal and mechanical properties of U3Si2: A combined ab-initio and molecular dynamics study

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

Contact Info

Product

Resources

About

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO₃^– and H₂O₂

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO₃^– and H₂O₂