Performance of U3Si2 in an LWR following a cladding breach during normal operation

Sweet, Ryan T.; Yang, Ying; Terrani, Kurt A.; Wirth, Brian; Nelson, Andrew

doi:10.1016/j.jnucmat.2020.152263

Title: Performance of U₃Si₂ in an LWR following a cladding breach during normal operation

Journal Article · Wed Jun 17 00:00:00 EDT 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152263· OSTI ID:1649345

Sweet, Ryan T. ^[1];

^[2];

^[2]; Wirth, Brian ^[3];

^[2]

Univ. of Tennessee, Knoxville, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

High-density fuels have been proposed as a possible replacement for uranium-dioxide as a fuel for light water reactors (LWRs) due to their increased loading of fissionable material. The objectives of this proposal are (1) to increase reactor cycle length and reactor power, and (2) to offset any neutronic penalty associated with advanced cladding systems. Of the high-density fuels under consideration, there is particular interest in triuranium disilicide (U₃Si₂) due to its increased metal density and favorable thermal properties as compared to UO₂. However, there are concerns regarding the chemical compatibility of U₃Si₂ with water and steam as used for LWR coolant.This paper summarizes research on fuel-coolant chemical compatibility for UO₂ LWR fuel during a cladding breach and highlights that generally, because of its chemical inertness, UO₂-coolant reactions are of little consequence to reactor operation. However, the volumetric expansion associated with the reaction of UO₂ and oxygen is a concern for possible conditions encountered during air ingress of dry storage. These same concerns arise for U₃Si₂, which exhibits greater volumetric expansion than UO₂ when exposed to water or steam. These reactions ultimately result in increased fuel volume that the cladding must accommodate, as well as additional heat generated as the fuel reacts.The BISON fuel performance code was used to perform a comparative analysis on the behavior of UO₂ and U₃Si₂ under normal operation. Silicide fuel simulations were then extended to demonstrate how varying thermodynamic and chemical kinetics influence fuel expansion and subsequent cladding performance during a cladding breach. These simulations were further extended to a 3D subsection of a fuel rod to demonstrate the characteristics of the resulting cladding crack.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1649345

Alternate ID(s):: OSTI ID: 1637363

Journal Information:: Journal of Nuclear Materials, Vol. 539, Issue 1; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 11 works

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References (41)

Preliminary evaluation of U 3 Si 2 -FeCrAl fuel performance in light water reactors through a multi-physics coupled way He, Yanan; Chen, Ping; Wu, Yingwei Nuclear Engineering and Design, Vol. 328 https://doi.org/10.1016/j.nucengdes.2017.12.019	journal	March 2018
Multidimensional multiphysics simulation of nuclear fuel behavior Williamson, R. L.; Hales, J. D.; Novascone, S. R. Journal of Nuclear Materials, Vol. 423, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.01.012	journal	April 2012
The aqueous corrosion of reactor metals Wanklyn, J. N.; Jones, P. J. Journal of Nuclear Materials, Vol. 6, Issue 3 https://doi.org/10.1016/0022-3115(62)90006-5	journal	August 1962
Oxidation of U-10 at% Zr alloy in air at 432–1028 K Matsui, Tsuneo; Yamada, Takanobu Journal of Nuclear Materials, Vol. 210, Issue 1-2 https://doi.org/10.1016/0022-3115(94)90235-6	journal	June 1994
The Thermo-Calc databank system Sundman, Bo; Jansson, Bo; Andersson, Jan-Olof Calphad, Vol. 9, Issue 2 https://doi.org/10.1016/0364-5916(85)90021-5	journal	April 1985
Determination of elastic properties of polycrystalline U3Si2 using resonant ultrasound spectroscopy Carvajal-Nunez, U.; Saleh, T. A.; White, J. T. Journal of Nuclear Materials, Vol. 498 https://doi.org/10.1016/j.jnucmat.2017.11.008	journal	January 2018
Oxidation of spent fuel in air at 175 to 195°C Einziger, R. E.; Thomas, L. E.; Buchanan, H. C. Journal of Nuclear Materials, Vol. 190 https://doi.org/10.1016/0022-3115(92)90075-V	journal	August 1992
Solution of hydrogen in accident tolerant fuel candidate material: U3Si2 Middleburgh, S. C.; Claisse, A.; Andersson, D. A. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2018.01.018	journal	April 2018
Postirradiation Behavior of UO ₂ Fuel I: Elements at 220 to 250°C in Air Novak, J.; Hastings, Ian J.; Mizzan, Elio Nuclear Technology, Vol. 63, Issue 2 https://doi.org/10.13182/NT83-A33285	journal	November 1983
U3Si2 behavior in H2O environments: Part II, pressurized water with controlled redox chemistry Nelson, A. T.; Migdisov, A.; Wood, E. Sooby Journal of Nuclear Materials, Vol. 500 https://doi.org/10.1016/j.jnucmat.2017.12.026	journal	March 2018
Steam oxidation of fuel in defective LWR rods Olander, D. R.; Soo Kim, Yeon; Wang, Wei-E Journal of Nuclear Materials, Vol. 270, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00759-4	journal	April 1999
Fuel oxidation and irradiation behaviors of defective BWR fuel rods Une, K.; Imamura, M.; Amaya, M. Journal of Nuclear Materials, Vol. 223, Issue 1 https://doi.org/10.1016/0022-3115(94)00693-8	journal	May 1995
A conceptual model for the fuel oxidation of defective fuel Higgs, J. D.; Lewis, B. J.; Thompson, W. T. Journal of Nuclear Materials, Vol. 366, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2006.12.050	journal	June 2007
The Canadian Spent Fuel Storage Canister: Some Materials Aspects Boase, Derek G.; Vandergraaf, Tjalle T. Nuclear Technology, Vol. 32, Issue 1 https://doi.org/10.13182/NT77-A31738	journal	January 1977
Fuel Performance and Fission Product Release Studies for Defected Fuel Elements Lewis, Brent J.; MacDonald, Roderick D.; Ivanoff, Nicholas V. Nuclear Technology, Vol. 103, Issue 2 https://doi.org/10.13182/NT93-A34845	journal	August 1993
Characterization of fuel oxidation in rods with clad-holes Verrall, R. A.; He, Z.; Mouris, J. F. Journal of Nuclear Materials, Vol. 344, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2005.04.049	journal	September 2005
Studies of the kinetics and mechanism of the oxidation of uranium by dry and moist air A model for determining the oxidation rate over a wide range of temperatures and water vapour pressures McGillivray, G. W.; Geeson, D. A.; Greenwood, R. C. Journal of Nuclear Materials, Vol. 208, Issue 1-2 https://doi.org/10.1016/0022-3115(94)90200-3	journal	January 1994
High temperature oxidation of UO2 in steam-hydrogen mixtures Abrefah, J.; Aguiar Braid, A. de; Wang, W. Journal of Nuclear Materials, Vol. 208, Issue 1-2 https://doi.org/10.1016/0022-3115(94)90201-1	journal	January 1994
Hydrogen absorption in U 3 Si 2 and its impact on electronic properties Mašková, Silvie; Miliyanchuk, Khrystyna; Havela, Ladislav Journal of Nuclear Materials, Vol. 487 https://doi.org/10.1016/j.jnucmat.2017.02.036	journal	April 2017
Oxidation of uranium mononitride and uranium monocarbide Dell, R. M.; Wheeler, V. J.; McIver, E. J. Transactions of the Faraday Society, Vol. 62 https://doi.org/10.1039/tf9666203591	journal	January 1966
Sensitivity of measured steam oxidation kinetics to atmospheric control and impurities Sooby Wood, E.; Terrani, K. A.; Nelson, A. T. Journal of Nuclear Materials, Vol. 477 https://doi.org/10.1016/j.jnucmat.2016.05.023	journal	August 2016
Corrigendum to “Thermophysical properties of U3Si2 to 1773 K” [J. Nucl. Mater. 464 (2015) 275–280] White, J. T.; Nelson, A. T.; Dunwoody, J. T. Journal of Nuclear Materials, Vol. 484 https://doi.org/10.1016/j.jnucmat.2016.11.015	journal	February 2017
A detailed study of UO2 to U3O8 oxidation phases and the associated rate-limiting steps Rousseau, G.; Desgranges, L.; Charlot, F. Journal of Nuclear Materials, Vol. 355, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.03.015	journal	September 2006
Current knowledge on core degradation phenomena, a review Hofmann, P. Journal of Nuclear Materials, Vol. 270, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00899-X	journal	April 1999
Oxidation behavior of U-Si compounds in air from 25 to 1000 C Sooby Wood, E.; White, J. T.; Nelson, A. T. Journal of Nuclear Materials, Vol. 484 https://doi.org/10.1016/j.jnucmat.2016.12.016	journal	February 2017
The Behavior of Breached Boiling Water Reactor Fuel Rods on Long-Term Exposure to Air and Argon at 598 K Kohli, R.; Stahl, D.; Pasupathi, V. Nuclear Technology, Vol. 69, Issue 2 https://doi.org/10.13182/NT85-A33630	journal	May 1985
Oxidation of Fuel Rod under Dry Storage Condition Nakamura, Jinichi; Otomo, Takashi; Kikuchi, Teruo Journal of Nuclear Science and Technology, Vol. 32, Issue 4 https://doi.org/10.1080/18811248.1995.9731712	journal	April 1995
Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°C Einziger, Robert E.; Cook, James A. Nuclear Technology, Vol. 69, Issue 1 https://doi.org/10.13182/NT85-A33595	journal	April 1985
Initial validation of a fuel oxidation model with an out-reactor instrumented defected fuel experiment Quastel, Aaron D.; Thiriet, Catherine M.; Abbasian, Farzin Journal of Nuclear Materials, Vol. 508 https://doi.org/10.1016/j.jnucmat.2018.05.029	journal	September 2018
U3Si2 behavior in H2O: Part I, flowing steam and the effect of hydrogen Wood, E. Sooby; White, J. T.; Grote, C. J. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2018.01.002	journal	April 2018
An X-ray diffraction study of the formation of β-UO2.33 on UO2 pellet surfaces in air at 229 to 275°C Taylor, Peter; Burgess, Elizabeth A.; Owen, Derrek G. Journal of Nuclear Materials, Vol. 88, Issue 1 https://doi.org/10.1016/0022-3115(80)90395-5	journal	January 1980
The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents Terrani, Kurt A.; Wang, Dean; Ott, Larry J. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.051	journal	May 2014
Accident tolerant fuel cladding development: Promise, status, and challenges Terrani, Kurt A. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2017.12.043	journal	April 2018
Irradiation behaviour of uranium silicide compounds Finlay, M. R.; Hofman, G. L.; Snelgrove, J. L. Journal of Nuclear Materials, Vol. 325, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2003.11.009	journal	February 2004
The behaviour of defective reactor fuel Locke, D. H. Nuclear Engineering and Design, Vol. 21, Issue 2 https://doi.org/10.1016/0029-5493(72)90080-5	journal	January 1972
In-reactor degradation of fuel and cladding in fuel pins operated with weld defects Mishra, Prerna; Jathar, V. P.; Singh, J. L. Journal of Nuclear Materials, Vol. 439, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.05.033	journal	August 2013
Thermophysical properties of $U_{3} {Si}_{2}$ to 1773 K White, J. T.; Nelson, A. T.; Dunwoody, J. T. Journal of Nuclear Materials, Vol. 464 https://doi.org/10.1016/j.jnucmat.2015.04.031	journal	September 2015
Enthalpy of formation of U3Si2: A high-temperature drop calorimetry study Guo, Xiaofeng; White, Joshua T.; Nelson, Andrew T. Journal of Nuclear Materials, Vol. 507 https://doi.org/10.1016/j.jnucmat.2018.04.032	journal	August 2018
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions Barani, T.; Pastore, G.; Pizzocri, D. Journal of Nuclear Materials, Vol. 522 https://doi.org/10.1016/j.jnucmat.2019.04.037	journal	August 2019
Properties and structure of vitreous silica. I Brückner, R. Journal of Non-Crystalline Solids, Vol. 5, Issue 2 https://doi.org/10.1016/0022-3093(70)90190-0	journal	November 1970
Postirradiation examinations of low burnup U3Si2 fuel for light water reactor applications Cappia, Fabiola; Harp, Jason M. Journal of Nuclear Materials, Vol. 518 https://doi.org/10.1016/j.jnucmat.2019.02.047	journal	May 2019

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Title: Performance of U₃Si₂ in an LWR following a cladding breach during normal operation