Continuum model for hydrogen pickup in zirconium alloys of LWR fuel cladding

AbstractWe present a kinetic model for solid state phase transformation ($$\alpha \rightleftharpoons \beta$$ α ⇌ β ) of common zirconium alloys used as fuel cladding material in light water reactors. The model computes the relative amounts of $$\beta$$ β or $$\alpha$$ α phase fraction as a function of time or temperature in the alloys. The model accounts for the influence of excess oxygen (due to oxidation) and hydrogen concentration (due to hydrogen pickup) on phase transformation kinetics. Two variants of the model denoted by A and B are presented. Model A is suitable for simulation of laboratory experiments in which the heating/cooling rate is constant and is prescribed. Model B is more generic. We compare the results of our model computations, for both A and B variants, with accessible experimental data reported in the literature covering heating/cooling rates of up to 100 K/s. The results of our comparison are satisfactory, especially for model A. Our model B is intended for implementation in fuel rod behavior computer programs, applicable to a reactor accident situation, in which the Zr-based fuel cladding may go through $$\alpha \rightleftharpoons \beta$$ α ⇌ β phase transformation.

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Hydrogen Pickup During Aqueous Corrosion Of Zirconium Alloys

CORROSION ◽

10.5006/0010-9312-17.3.81 ◽

1961 ◽

Vol 17 (3) ◽

pp. 109t-117t ◽

Cited By ~ 33

Author(s):

WARREN E. BERRY ◽

DALE A. VAUGHAN ◽

EARL L. WHITE

Keyword(s):

Zirconium Alloys ◽

Aqueous Corrosion ◽

Hydrogen Pickup

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Hydrogen Pickup Mechanism in Zirconium Alloys

Zirconium in the Nuclear Industry: 18th International Symposium ◽

10.1520/stp159720160055 ◽

2018 ◽

pp. 312-349

Author(s):

Adrien Couet ◽

Arthur T. Motta ◽

Antoine Ambard ◽

Robert J. Comstock

Keyword(s):

Zirconium Alloys ◽

Hydrogen Pickup

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Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

Annual Review of Materials Research ◽

10.1146/annurev-matsci-070214-020951 ◽

2015 ◽

Vol 45 (1) ◽

pp. 311-343 ◽

Cited By ~ 155

Author(s):

Arthur T. Motta ◽

Adrien Couet ◽

Robert J. Comstock

Keyword(s):

Nuclear Fuel ◽

Zirconium Alloys ◽

Fuel Cladding ◽

Nuclear Fuel Cladding

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Performance degradation of candidate accident-tolerant cladding under corrosive environment

Corrosion Reviews ◽

10.1515/corrrev-2017-0014 ◽

2017 ◽

Vol 35 (3) ◽

pp. 129-140 ◽

Cited By ~ 7

Author(s):

Fumihisa Nagase ◽

Kan Sakamoto ◽

Shinichiro Yamashita

Keyword(s):

Nuclear Power ◽

Fission Products ◽

Zirconium Alloys ◽

Performance Degradation ◽

Lessons Learned ◽

Light Water Reactor ◽

Fuel Cladding ◽

Power Station ◽

Light Water ◽

Fukushima Daiichi

AbstractLight-water reactor (LWR) fuel cladding shall retain the performance as the barrier for nuclear fuel materials and fission products in high-pressure and high-temperature coolant under irradiation conditions for long periods. The cladding also has to withstand temperature increase and severe loading under accidental conditions. As lessons learned from the accident at the Fukushima Daiichi nuclear power station, advanced cladding materials are being developed to enhance accident tolerance compared to conventional zirconium alloys. The present paper reviews the progress of the development and summarizes the subjects to be solved for enhanced accident-tolerant fuel cladding, focusing on performance degradation under various corrosive environmental conditions that should be considered in designing the LWR fuel.

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Reducing Hydrogen Penetration through Corrosion Layer Formed on Zirconium Alloys by Iron Addition

Advances in Science and Technology ◽

10.4028/www.scientific.net/ast.45.1980 ◽

2006 ◽

Vol 45 ◽

pp. 1980-1985

Author(s):

Kazuo Kakiuchi ◽

Kazutoshi Okubo ◽

Noboru Itagaki ◽

Akihiro Miyazaki ◽

Yoshiaki Ishii ◽

...

Keyword(s):

Hydrogen Absorption ◽

Electrical Potential ◽

Potential Gradient ◽

Zirconium Alloys ◽

Corrosion Layer ◽

Potential Measurement ◽

Irradiation Experiment ◽

Hydrogen Pickup ◽

Hydrogen Penetration ◽

Iron Addition

Latest post-irradiation experiment results of Zry-2 and HiFi alloy (0.4%Fe-Zry2) showed that iron addition reduces the hydrogen pickup by these alloys compared to oxidation amount. In order to clarify the mechanism of reduced hydrogen absorption rate, (1) autoclave test, (2) surface potential measurement and (3) hydrogen absorption test of the intermetallic compound were carried out. Based on these results, a tentative mechanism for hydrogen absorption by zirconium alloys is proposed, taking into account of both the electrical potential gradient over the oxide film as well as the SPP window for hydrogen absorption.

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Phase transformation of the corrosion layers on nuclear fuel cladding. Raman spectroscopy study.

Paliva ◽

10.35933/paliva.2021.04.01 ◽

2021 ◽

pp. 113-117

Author(s):

Kryštof Frank ◽

Ladislav Lapčák ◽

Jan Macák

Keyword(s):

Raman Spectroscopy ◽

Zirconium Oxide ◽

Nuclear Reactors ◽

Relative Proportion ◽

Protective Layer ◽

Zirconium Alloys ◽

Corrosion Layer ◽

Spectroscopy Study ◽

Fuel Cladding ◽

Nuclear Fuel Cladding

The goal of this work was the phase analysis of corrosion layers on zirconium alloys. In the environment of nuclear reactors, zirconium alloys are covered with a protective layer of zirconium oxide, which occurs in two crystalline modifications - monoclinic and tetragonal. The distribution of these phases in the corrosion layer can affect the overall corrosion rate. Raman spectroscopy was used to determine the composition of the corrosion layers. The use of this method is advantageous because the monoclinic and tetragonal phases can be easily distinguished in the spectra of the corrosion layers. In total, samples of two alloys were measured. The samples were pre-exposed at 360 °C in Li+ containing water (70 mg/l Li as LiOH) . Exposure times were between 21 d and 231 d, so the series contained both pre- and post- transition samples. The relative proportion of the tetragonal phase decreases significantly after the transient. It has also been found that the corrosion layers are highly heterogeneous in terms of the distribution of crystalline modifications.

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