Fretting wear comparison of cladding materials for reactor fuel cladding application

Winter, Thomas; Neu, Richard W.; Singh, Preet M.; Kolaya, L.E.; Deo, Chaitanya

doi:10.1016/j.jnucmat.2018.05.069

Cited by 29 publications

(6 citation statements)

References 14 publications

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“…The fretting wear of alloy 690 Corresponding author's e-mail: kondo.m.ai@m.titech.ac.jp tubes against 304 stainless steel plates was reported in the previous study [9]. Fretting studies were also performed to examine the reliability of cladding materials (e.g., APMT, SiC and Zircaloy-4 [10]).…”

Section: Introductionmentioning

confidence: 90%

Effect of Temperature on Fretting Corrosion Behaviors between Li2TiO3 Pebble and F82H

MASAKI

Kondo

KIM

et al. 2022

Plasma and Fusion Research

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Lithium titanate (Li 2 TiO 3 ) pebble is a candidate tritium breeder of solid breeder blanket systems of fusion reactors. The oscillation of coolant tubes can be induced by the coolant flow. Fretting corrosion is caused between the Li 2 TiO 3 pebbles and the coolant tubes which are made of reduced activation ferritic martensitic steel F82H. The purpose of the present study is to clarify the fretting behaviors at the temperatures of blanket conditions. The Li 2 TiO 3 pebble produced by sol-gel method was pushed onto the surface of the oscillating F82H plate in the fretting tests which were performed for 10 min in an air atmosphere up to 573 K. The fretting scars of the Li 2 TiO 3 pebble and the F82H plate were observed and analyzed by SEM/EDX and 3D laser scanning microscope. The fretting wear was mitigated at the temperatures of 373 K and 473 K due to the formation of the oxide layer, which might reduce the friction. The pebble was partially destructed by the fretting motion in the test performed at 573 K. The fretting wear of the pebble and the F82H plate was mitigated when the pebble was not fixed on the holder since the pebble could vibrate together with the oscillating plate.

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Section: Introductionmentioning

confidence: 90%

Effect of Temperature on Fretting Corrosion Behaviors between Li2TiO3 Pebble and F82H

MASAKI

Kondo

KIM

et al. 2022

Plasma and Fusion Research

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“…This fretting wear could be a result of grid-to-rod or by foreign debris. If a monolithic FeCrAl alloy cladding is used in place of the current Zr-based alloy cladding, it may seem intuitive, based on their relative mechanical properties in the vicinity of 300 • C, that the FeCrAl would offer better wear resistance than the Zr alloys [26,52].…”

Section: Fecral Alloys Are Resistant To Debris Frettingmentioning

confidence: 99%

Improved and Innovative Accident-Tolerant Nuclear Fuel Materials Considered for Retrofitting Light Water Reactors—A Review

Rebak

2023

CMD

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Since 2011, there has been an international effort to evaluate the behavior of newer fuel rod materials for the retrofitting of existing light water reactors (LWR). These materials include concepts for the cladding of the fuel and for the fuel itself. The materials can be broadly categorized into evolutionary or improved existing materials and revolutionary or innovative materials. The purpose of the newer materials or accident-tolerant fuels (ATF) is to make the LWRs more resistant to loss-of-coolant accidents and thus increase their operation safety. The benefits and detriments of the three main concepts for the cladding are discussed. These include (i) coatings for existing zirconium alloys; (ii) monolithic iron–chromium–aluminum alloys; and (iii) composites based on silicon carbide. The use of ATF materials may help extend the life of currently operating LWRs, while also being a link to material development for future commercial reactors.

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“…The fretting wear behavior of various kinds of zirconium alloys without shot peening has been studied in other environments (air, low temperature water or HTHPW) [20][21][22][23][24][25]. Cai and Zhou [26] reviewed the research about fretting wear of zirconium alloys and concluded that the testing environment is one of the most important parameters determining the fretting wear behavior.…”

Section: Introductionmentioning

confidence: 99%

Understanding the fretting corrosion mechanism of zirconium alloy exposed to high temperature high pressure water

Guo

Lai

et al. 2022

Corrosion Science

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Fretting wear comparison of cladding materials for reactor fuel cladding application

Cited by 29 publications

References 14 publications

Effect of Temperature on Fretting Corrosion Behaviors between Li<sub>2</sub>TiO<sub>3 </sub>Pebble and F82H

Effect of Temperature on Fretting Corrosion Behaviors between Li<sub>2</sub>TiO<sub>3 </sub>Pebble and F82H

Improved and Innovative Accident-Tolerant Nuclear Fuel Materials Considered for Retrofitting Light Water Reactors—A Review

Understanding the fretting corrosion mechanism of zirconium alloy exposed to high temperature high pressure water

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