This content will become publicly available on Tue Aug 06 00:00:00 EDT 2024
Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes
Abstract
Zirconium alloy tubes used as nuclear fuel cladding are subject to oxidation and subsequent hydrogen pickup during their long service in commercial light water reactors. The hydrogen picked up in the cladding can precipitate as a brittle hydride rim feature on the cladding outer surface. Here, to better understand the effect of hydride rims on the fracture behavior of stress-relieved zirconium alloy cladding tubes, a procedure to produce these rim-like structures has been developed and is described herein. Extensive characterization of the ‘as hydrided’ tubes is performed. The hydrogen charging apparatus consists of a tube furnace with a quartz chamber that is connected to a vacuum pump as well as a bottle of pure hydrogen gas. The charging station uses a static charge of hydrogen as opposed to a flowing gas. The chief advantage of this approach is the ability to monitor the pressure drop in the hydriding chamber and correlate this pressure drop to a known rate of hydrogen pickup in the cladding tube. It was found that the hydrogen partial pressure, metal temperature, and surface treatment all clearly played a role in whether a hydride rim was formed. Extensive characterization of the hydride rims shows they consist ofmore »
- Authors:
-
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign
- OSTI Identifier:
- 2283323
- Alternate Identifier(s):
- OSTI ID: 1994213
- Report Number(s):
- INL/JOU-23-71793-Revision-0
Journal ID: ISSN 0022-3115
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 586; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; zirconium; zirconium hydride; nuclear fuel cladding
Citation Formats
Kamerman, David W., Bachhav, Mukesh, Yao, Tiankai, Pu, Xiaofei, and Burns, Jatuporn. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. United States: N. p., 2023.
Web. doi:10.1016/j.jnucmat.2023.154675.
Kamerman, David W., Bachhav, Mukesh, Yao, Tiankai, Pu, Xiaofei, & Burns, Jatuporn. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes. United States. https://doi.org/10.1016/j.jnucmat.2023.154675
Kamerman, David W., Bachhav, Mukesh, Yao, Tiankai, Pu, Xiaofei, and Burns, Jatuporn. Sun .
"Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes". United States. https://doi.org/10.1016/j.jnucmat.2023.154675.
@article{osti_2283323,
title = {Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes},
author = {Kamerman, David W. and Bachhav, Mukesh and Yao, Tiankai and Pu, Xiaofei and Burns, Jatuporn},
abstractNote = {Zirconium alloy tubes used as nuclear fuel cladding are subject to oxidation and subsequent hydrogen pickup during their long service in commercial light water reactors. The hydrogen picked up in the cladding can precipitate as a brittle hydride rim feature on the cladding outer surface. Here, to better understand the effect of hydride rims on the fracture behavior of stress-relieved zirconium alloy cladding tubes, a procedure to produce these rim-like structures has been developed and is described herein. Extensive characterization of the ‘as hydrided’ tubes is performed. The hydrogen charging apparatus consists of a tube furnace with a quartz chamber that is connected to a vacuum pump as well as a bottle of pure hydrogen gas. The charging station uses a static charge of hydrogen as opposed to a flowing gas. The chief advantage of this approach is the ability to monitor the pressure drop in the hydriding chamber and correlate this pressure drop to a known rate of hydrogen pickup in the cladding tube. It was found that the hydrogen partial pressure, metal temperature, and surface treatment all clearly played a role in whether a hydride rim was formed. Extensive characterization of the hydride rims shows they consist of needle like platelets of δ phase hydrides (ZrH1.66) oriented in the circumferential direction with a radial spacing of several microns in a sandwich-like structure.},
doi = {10.1016/j.jnucmat.2023.154675},
journal = {Journal of Nuclear Materials},
number = ,
volume = 586,
place = {United States},
year = {Sun Aug 06 00:00:00 EDT 2023},
month = {Sun Aug 06 00:00:00 EDT 2023}
}
Works referenced in this record:
Corrosion of Zirconium Alloys
book, January 2012
- Allen, T. R.; Konings, R. J. M.; Motta, A. T.
- Comprehensive Nuclear Materials
Effects of hydride rim on the ductility of Zircaloy-4 cladding
journal, September 2019
- Kim, Ju-Seong; Kim, Ho-A; Kang, So-Young
- Journal of Nuclear Materials, Vol. 523
Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction
journal, August 2009
- Daum, R. S.; Chu, Y. S.; Motta, A. T.
- Journal of Nuclear Materials, Vol. 392, Issue 3
Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions
journal, February 2013
- Billone, M. C.; Burtseva, T. A.; Einziger, R. E.
- Journal of Nuclear Materials, Vol. 433, Issue 1-3
Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes
journal, June 2014
- Hellouin de Menibus, Arthur; Auzoux, Quentin; Dieye, Ousmane
- Journal of Nuclear Materials, Vol. 449, Issue 1-3
Cracking and spalling of the oxide layer developed in high-burnup Zircaloy-4 cladding under normal operating conditions in a PWR
journal, December 2018
- Hong, Kisik; Barber, J. R.; Thouless, M. D.
- Journal of Nuclear Materials, Vol. 512
Hydrogen supercharging in Zircaloy
journal, June 1971
- Marino, G. P.
- Materials Science and Engineering, Vol. 7, Issue 6
Diffusion coefficient of hydrogen in alpha zirconium, Zircaloy-2 and Zircaloy-4
journal, June 1972
- Kearns, J. J.
- Journal of Nuclear Materials, Vol. 43, Issue 3
Hydride Rim Formation in E110 Zirconium Alloy during Gas-Phase Hydrogenation
journal, February 2020
- Kudiiarov, Viktor; Sakvin, Ivan; Syrtanov, Maxim
- Metals, Vol. 10, Issue 2
Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test
journal, January 2005
- Nagase, Fumihisa; Fuketa, Toyoshi
- Journal of Nuclear Science and Technology, Vol. 42, Issue 1
Improved-EDC tests on the Zircaloy-4 cladding tube with an outer surface pre-crack
journal, December 2015
- Shinozaki, Takashi; Udagawa, Yutaka; Mihara, Takeshi
- Journal of Nuclear Science and Technology, Vol. 53, Issue 9
Fuel cladding behavior under rapid loading conditions
journal, February 2016
- Yueh, K.; Karlsson, J.; Stjärnsäter, J.
- Journal of Nuclear Materials, Vol. 469
Influence of Cladding-Peripheral Hydride on Mechanical Fuel Failure under Reactivity-Initiated Accident Conditions
journal, May 2007
- Tomiyasu, Kunihiko; Sugiyama, Tomoyuki; Fuketa, Toyoshi
- Journal of Nuclear Science and Technology, Vol. 44, Issue 5
Gamma-zirconium hydride on DHC fracture surfaces is a legitimate stable phase, not a metastable phase
journal, May 2021
- Coleman, C. E.; McRae, G. A.; Buyers, A.
- Journal of Nuclear Materials, Vol. 548
Hydride precipitation, fracture and plasticity mechanisms in pure zirconium and Zircaloy-4 at temperatures typical for the postulated loss-of-coolant accident
journal, May 2016
- Pshenichnikov, Anton; Stuckert, Juri; Walter, Mario
- Nuclear Engineering and Design, Vol. 301
Hydride Formation in Zirconium Alloys
journal, October 2012
- Motta, Arthur T.; Chen, Long-Qing
- JOM, Vol. 64, Issue 12
Hydrides in zirconium-2.5 wt. % niobium alloy pressure tubing
journal, November 1978
- Northwood, D. O.; Gilbert, R. W.
- Journal of Nuclear Materials, Vol. 78, Issue 1