Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel

Reed, Brady; Wang, Rick; Lu, Roger Y.; Qu, Jun

doi:10.1016/j.wear.2020.203578

Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel

Journal Article · Sun Dec 13 00:00:00 EST 2020 · Wear

DOI:https://doi.org/10.1016/j.wear.2020.203578· OSTI ID:1756262

^[1]; ^[1]; Lu, Roger Y. ^[2]; ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
Westinghouse Electric Company, Hopkins, SC (United States)

In pressurized water reactors (PWRs), water flow induced vibrations cause contact and rubbing between the fuel rods and the supporting grid, a phenomenon known as Grid-to-Rod-Fretting (GTRF). GTRF may produce progressive wear damage on the fuel claddings leading to subsequent leakage of radioactive fission products. Various accident-tolerant fuel (ATF) concepts are being developed for higher resistance to the high temperature steam and one approach is to apply a cladding coating. Here, fretting wear behavior of a candidate Cr-coating was investigated using a unique bench-scale autoclave testing rig mimicking the environment in an industrial full-assembly PWR simulator. The contact was under a realistically low load (~0.5 N) lubricated by deionized water at a temperature of 204 °C under a pressure of 20-23 bars. Results demonstrated that the Cr-coating significantly improved the cladding's wear resistance when tested against a commercial ZIRLO grid with or without pre-oxidization. In addition, the Cr-coating also reduced wear on the non-oxidized ZIRLO grid but slightly increased the wear on the pre-oxidized grid.

View Accepted Manuscript (DOE)

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

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

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1756262

Alternate ID(s):: OSTI ID: 1776259

Journal Information:: Wear, Journal Name: Wear Vol. 466-467; ISSN 0043-1648

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Cr-coating
accident-tolerant fuel (ATF)
autoclave
grid-to-rod-fretting (GTRF)
pressurized water reactors (PWRs)
wear

Autoclave grid-to-rod fretting wear evaluation of a candidate cladding coating for accident-tolerant fuel

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References (18)

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