High temperature mechanical properties of fluorite crystal structured materials (CeO2, ThO2, and UO2) and advanced accident tolerant fuels (U3Si2, UN, and UB2)

Frazer, D.; Maiorov, B.; Carvajal-Nunez, Ursula; Evans, Jordan A.; Kardoulaki, Erofili; Dunwoody, J.; Saleh, Tarik A.; White, Joshua T.

doi:10.1016/j.jnucmat.2021.153035

Cited by 21 publications

(2 citation statements)

References 57 publications

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“…The results of room temperature nanoindentation on fresh UO 2 fuels shows hardness values between 9.5 and 12.5 GPa [31,54,55] depending on the microstructure and manufacturing route of the UO 2 . In this work at room temperature, the hardness varies between 6 and 12 GPa depending on the location of the indent.…”

Section: Discussionmentioning

confidence: 99%

Post-irradiation examination of legacy high burnup fuel to support safety testing

Cappia,

Pavlov,

Frazer

et al. 2021

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Section: Discussionmentioning

confidence: 99%

Post-irradiation examination of legacy high burnup fuel to support safety testing

Cappia,

Pavlov,

Frazer

et al. 2021

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“…This means that fuels with higher U densities need to be implemented instead of traditional UO 2 to achieve similar neutronic performance as that of the UO 2 -Zr system. For this reason, uranium silicides have been previously explored by Westinghouse Electric and more recently uranium mononitride [10,11]. It is obvious then that when deciding on a cladding substitution for a reactor system, the fuel is also a crucial component that cannot be ignored.…”

Section: Introductionmentioning

confidence: 99%

Carburization Kinetics of Zircalloy-4 and Its Implication for Small Modular Reactor Performance

et al. 2022

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Carburization of cladding materials has long been a concern for the nuclear industry and has led to the restricted use of high-thermal conductivity fuels such as uranium carbides. With the rise of small modular reactors (SMRs) that frequently implement a graphite core-block, carburization of reactor components is once more in the foreground as a potential failure mechanism. To ensure commercial viability for SMRs, neutron-friendly cladding materials such as Zr-based alloys are required. In this work, the carburization kinetics of Zircaloy-4 (Zry-4), for the temperature range 1073–1673 K (covering typical operating temperatures and off-normal scenarios) are established. The following Arrhenius relationship for the parabolic constant describing ZrC growth is derived: Kp (in μm2/s) = 609.35 exp(−1.505 × 105/RT)). Overall, the ZrC growth is sluggish below 1473 K which is within the operational temperature range of SMRs. In all cases the ZrC that forms from solid state reaction is hypo-stoichiometric, as confirmed through XRD. The hardness and elastic modulus of carburized Zry-4 are also examined and it is shown that despite the formation of a ZrC layer, C ingress in the Zry-4 bulk does not impact the mechanical response after carburization at 1073 K and 1473 K for 96 h.

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Assessing the Effect of Some ATF Materials and Uncertainties on Their Properties Under Normal Operation Conditions by Means of the Transuranus Code

Uffelen

Arndt

Soti

2023

Springer Proceedings in Physics

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High temperature mechanical properties of fluorite crystal structured materials (CeO2, ThO2, and UO2) and advanced accident tolerant fuels (U3Si2, UN, and UB2)

Cited by 21 publications

References 57 publications

Post-irradiation examination of legacy high burnup fuel to support safety testing

Post-irradiation examination of legacy high burnup fuel to support safety testing

Carburization Kinetics of Zircalloy-4 and Its Implication for Small Modular Reactor Performance

Assessing the Effect of Some ATF Materials and Uncertainties on Their Properties Under Normal Operation Conditions by Means of the Transuranus Code

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