Wettability and CHF limits of Accident-Tolerant nuclear fuel cladding materials in light water reactor conditions

Su, Guosheng; Moreira, Tiago Augusto; Lee, Donghoon; Jena, A. K.; Wang, G.; Byers, A.; Phillips, Brent; Karoutas, Zeses; Anderson, Mark; Bucci, Matteo

doi:10.1016/j.applthermaleng.2022.119018

Cited by 11 publications

(3 citation statements)

References 49 publications

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“…Another study carried out by Su et al [15] analyzed the critical heat flux (CHF)-HF is a limiting heat flux at which the heated surface can no longer maintain continuous liquid contact-on chromium-coated zirconium alloy and bare zirconium alloy surfaces. The authors found that the chromium surface and the bare zirconium alloy surface had similar wettability and that there was practically no difference in the steady-state CHF limits, both under low-pressure and high-pressure conditions.…”

Section: Effect Of Coating On Heat Transfermentioning

confidence: 99%

Initial Multidisciplinary Study of Oxidized Chromium-Coated Zirconium Alloy for Fuel Cladding of SCW-SMR Concept: Weight-Gain and Thermal Conductivity Measurements and Coating Cost Evaluation

Khumsa-Ang,

Mendoza,

Nava-Dominguez

et al. 2023

Coatings

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One of the challenges of small modular reactors (SMRs) in comparison with large reactors is the greater difficulty in achieving high burnups in smaller cores. With greater neutron leakage through the periphery, a key factor is the neutron economy of the fuel cladding. However, all large supercritical water-cooled reactor (SCWR) concepts have employed neutron-absorbing stainless steels and nickel-based alloys in order to meet all the requirements in terms of corrosion and thermalhydraulics. In order to achieve higher burnups and extend the time between refueling in a SCW-SMR, the use of chromium-coated zirconium alloy as a potential fuel cladding candidate has been explored. Chromium coatings up to a few micrometers thick have shown improved oxidation resistance of zirconium-based claddings under operating conditions relevant to SCWR concepts. In this study, Zr-2.5Nb alloy (UNS R60904) from pressure tube samples was coated using a physical vapor-deposition (PVD) method. Oxidation tests were performed on coated samples at 500 °C and approximately 25 MPa in a refreshed autoclave. The effects of the oxide on heat transfer and hydraulic resistance are also discussed in this study. Last, but not least, this study evaluates the coating cost of the fuel cladding with chromium in a vacuum plasma spray process.

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Section: Effect Of Coating On Heat Transfermentioning

confidence: 99%

Initial Multidisciplinary Study of Oxidized Chromium-Coated Zirconium Alloy for Fuel Cladding of SCW-SMR Concept: Weight-Gain and Thermal Conductivity Measurements and Coating Cost Evaluation

Khumsa-Ang,

Mendoza,

Nava-Dominguez

et al. 2023

Coatings

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“…Given the importance of wetting and spreading behaviors of water in high-temperature and high-pressure applications, such as boiling heat transfer in nuclear reactors, spray cooling, and carbon geo-storage, the temperature dependence of the contact angles of water has been explored since the 1960s. , A recent review provided a state-of-the-art review on this topic by focusing on how temperature affects the wetting behavior of water on solid surfaces.…”

Section: Introductionmentioning

confidence: 99%

“…Bernardin et al measured the SCA of water on an aluminum surface at temperatures up to 170 °C and pressures up to 0.84 MPa and observed two distinct temperature-dependent regimes. To explore the temperature dependence under higher temperature and pressure conditions, the pressure vessels capable of reaching higher parameters were designed by the group of Takamasa, − the group of Bucci, , and the group of Fan. − In these studies, the temperature dependence of the contact angle of water on metal surfaces such as stainless steel, aluminum, and zircaloy was investigated under elevated temperatures up to 300 °C and elevated pressures up to 15 MPa. Despite the slight quantitative difference, the temperature dependence of the contact angles of water has a good qualitative agreement that it exhibits a piecewise-linearly decreasing trend as increasing the temperature.…”

Section: Introductionmentioning

confidence: 99%

Temperature Dependence of the Dynamic Contact Angles of Water on a Smooth Stainless-Steel Surface under Elevated Pressures

Fu,

Li,

Fan

2024

Langmuir

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The temperature dependence of the dynamic contact angles (DCAs) of water on a metallic surface remains unclear, especially under elevated pressures. Here in this work, the advancing and receding contact angles (RCAs), as well as the contact angle hysteresis (CAH), of water on stainless-steel 316 (SS316) surfaces were studied using the dynamic sessile drop method for temperatures up to 300 °C and pressures up to 10 MPa. It was found that the temperature dependence of the DCAs exhibits a different pattern as compared to the piecewise linear decline of static contact angles. The advancing contact angle (ACA) remains nearly constant and does not decrease until the temperature becomes close to the saturated temperature. The decrease in ACA is attributed to evaporation, which reduces the advancement of energy barrier. The RCA linearly declines below 120 °C and remains stable above 120 °C. The increasing temperature enhances the pinning effect and changes the droplet receding mode. Under all pressures tested, the CAH demonstrates a "increaseconstant-decrease" trilinear relationship with temperature. Furthermore, the mean solid surface entropy and solid−gas interfacial tension of SS316 were estimated to be 0.1152 mJ/(m 2 •°C) and 61.49 mJ/m 2 , respectively.

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Critical heat flux on zircaloy and accident tolerant fuel cladding under prototypical conditions of pressurized and boiling water reactors

Moreira

Lee

Anderson

2022

Applied Thermal Engineering

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Wettability and CHF limits of Accident-Tolerant nuclear fuel cladding materials in light water reactor conditions

Cited by 11 publications

References 49 publications

Initial Multidisciplinary Study of Oxidized Chromium-Coated Zirconium Alloy for Fuel Cladding of SCW-SMR Concept: Weight-Gain and Thermal Conductivity Measurements and Coating Cost Evaluation

Initial Multidisciplinary Study of Oxidized Chromium-Coated Zirconium Alloy for Fuel Cladding of SCW-SMR Concept: Weight-Gain and Thermal Conductivity Measurements and Coating Cost Evaluation

Temperature Dependence of the Dynamic Contact Angles of Water on a Smooth Stainless-Steel Surface under Elevated Pressures

Critical heat flux on zircaloy and accident tolerant fuel cladding under prototypical conditions of pressurized and boiling water reactors

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