journal article·2022-04Open access

Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding

Raul B. Rebak, Timothy B. Jurewicz, Michael Larsen, Liang Yin

Corrosion Science· Volume 198

Abstract

The use of accident tolerant fuels (ATF) will facilitate the continuing operation of light water reactors (LWR) by making them safer and more economical to operate. One of the ATF concepts is to use iron-chromium-aluminum (FeCrAl) alloys for the cladding of the fuel. These ferritic alloys were never used in power reactors before therefore their behavior needs to be characterized. Current results show a positive effect of zinc chemistry on the environmental degradation of ferritic FeCrAl. Autoclave tests at 288 °C show > 60% decrease in the dissolution rate of FeCrAl and 3–4 time decrease in the surface oxide film thickness.
Source: openalex_inverted_index · Quality: baseline

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (18)

Show source-provided references
1. Rebak · 2020
2. Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants10.1051/epjn/2017029 ↗
3. R.B. Rebak, T.B. Jurewicz, M. Larsen, K. Sakamoto, Immersion testing of FeCrAl tubes under simulated light water nuclear reactor normal operation conditions in: paper 184–30215, TopFuel 2019 Conference, American Nuclear Society, Seattle, Washington, 22–27 September 2019.
4. Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors10.1016/j.jnucmat.2021.153090 ↗
5. Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding10.1016/j.jnucmat.2020.152221 ↗
6. Uniform corrosion of FeCrAl alloys in LWR coolant environments10.1016/j.jnucmat.2016.06.047 ↗
7. Uniform corrosion behavior of FeCrAl alloys in borated lithiated high temperature water10.1016/j.jmst.2020.07.026 ↗
8. S. Odar, R. Cowan, J. Kysela, Effect of Zinc in BWR and PWR/VVER on Activity Build-up, IGSCC and Fuel Performance, ANT International, October 2010, Sweden.
9. C. Haas and D. Perkins, Zinc injection update, Nuclear Engineering International, 24 January 2011.
10. Corrosion mitigation in coolant systems in nuclear power plants10.1016/j.pnucene.2015.11.011 ↗
11. EPRI Report 1009568, Overview Report on Zinc Addition in Pressurized Water Reactors – 2004, Electric Power Research Institute, December 2004.
12. EPRI Report 1011313, Impact of Zinc Chemistry on PWR Primary Shutdown Dose Rates and Releases Following Steam Generator Replacement at Farley 1 and 2 (MRP-136), Electric Power Research Institute, February 2005.
13. Effect of zinc on the environmentally-assisted fatigue behavior of 316 stainless steels in simulated PWR primary environment10.1016/j.corsci.2019.02.012 ↗
14. Characterization of oxide layer formed on type 316 stainless steel exposed to the simulated PWR primary water environment with varying dissolved hydrogen and zinc concentrations10.1016/j.jnucmat.2021.153193 ↗
15. Effect of zinc addition scenarios on general corrosion of alloy 690 in borated and lithiated water at 330°C10.1016/j.corsci.2021.109627 ↗
16. Effect of zinc injection on the electrochemical behavior and crack growth rate of a 316 L stainless steel in simulated primary coolant of pressurized water reactors10.1016/j.matchar.2021.111177 ↗
17. Jurewicz · 2018
18. C. Lemaignan, Corrosion or zirconium alloy components in light water reactors, in: ASM Metals Handbook, Vol. 13C Corrosion: Environments and Industries, ASM International, Metals Park, OH, 2006, p. 415.10.31399/asm.hb.v13c.a0004148 ↗