Effect of surface oxides on tritium entrance and permeation in FeCrAl alloys for nuclear fuel cladding: a review

Garud, Yogendra S.; Rebak, Raul B.

doi:10.1515/corrrev-2022-0033

Effect of surface oxides on tritium entrance and permeation in FeCrAl alloys for nuclear fuel cladding: a review

Journal Article · 24 January 2023 · Corrosion Reviews (Online)

DOI:https://doi.org/10.1515/corrrev-2022-0033· OSTI ID:2418371

Garud, Yogendra S. ^[1]; Rebak, Raul B. ^[2]

Simrand LLC , San Jose , CA 95124 , USA; OSTI
GE Research , Schenectady , NY 12309 , USA

Abstract

Iron-chromium-aluminum (FeCrAl) alloys are being considered for the cladding of uranium dioxide fuel in light water reactors (LWRs). FeCrAl alloys have good mechanical properties at temperatures of 300 °C and higher, and have superlative resistance to attack by steam at temperatures of up to 1000 °C and higher. A concern has been raised that the use of FeCrAl for cladding would result in a higher content of tritium in the reactor coolant as compared with the current system where the cladding is a zirconium based alloy. This review shows that the flux of tritium from the fuel rod cavities to the coolant across the fuel cladding wall will be greatly reduced by the presence of oxides on the surface of the cladding. The review of current literature and permeation data show that (a) protective oxides are expected to be present on both sides of the FeCrAl cladding, and (b) depending on the characteristics of these oxide layers it is reasonable to expect about two–three orders of magnitude reduction in tritium permeation, relative to the permeation response in clean, unoxidized condition for FeCrAl steels of interest, around 277 °C–377 °C temperatures.

Research Organization:: GE Packaged Power, LLC, Houston, TX (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

DOE Contract Number:: NE0009047

OSTI ID:: 2418371

Journal Information:: Corrosion Reviews (Online), Journal Name: Corrosion Reviews (Online) Journal Issue: 2 Vol. 41; ISSN 2191-0316

Publisher:: De Gruyter

Country of Publication:: United States

Language:: English

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Materials Science
Metallurgy & Metallurgical Engineering

Effect of surface oxides on tritium entrance and permeation in FeCrAl alloys for nuclear fuel cladding: a review

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