Surface modification technology of fuel cladding, fresh green to mitigate corrosion and hydrogen-pickup in high-temperature steam environment

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

Fuel claddings would be exposed to a hightemperature steam-flow after a boiled-up sequence of a severe accident of light water reactors as well as spent fuel pools. Zirconium alloys are common cladding material for light water reactors. All the zirconium alloys generate additional heat by the exothermic reaction of oxidation in high-temperature steam. Subsequent temperature rise accelerates the rate of oxidation. The countermeasure to suppress oxidation of zirconium alloy is key to mitigate severe accidents. We invent a surface modification technology of zirconium alloy, Fresh Green, to oxidize and to carbonize a zirconium-alloy surface in the same process. XRD and XPS analyses indicated that a modified layer on zirconium surface is carbon-doped zirconium dioxide, in which some of oxygen atoms in monoclinic zirconium dioxide are replaced by carbon. Experiments are conducted for three representative conditions using an autoclave at relatively high temperature: uniform corrosion at 400 degrees Celsius for 336 hours, nodular corrosion at 500 degrees Celsius for 24 hours, supercritical water corrosion (at 400 degrees Celsius, 24 hours). The Fresh Green surface modification reduces both the oxidation rate and hydrogen-pickup less than a half of that with untreated base material. This is because the Fresh Green layer is closely packed and adhered intimately to the base material. Hydrides were found in the base material without treatment, though they were scarcely observed in the Fresh Green treated specimen. Since the operating temperature of the Fresh Green process is lower than the final annealing temperature in a manufacturing process, the process does not affect the material property and crystal structure. The Fresh Green process, which can be operated at slightly higher pressure than ambient, can be introduced in the conventional manufacturing process without complicity.

Original languageEnglish
Title of host publication2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
PublisherInternational Congress on Advances in Nuclear Power Plants, ICAPP
ISBN (Electronic)9784890471676
Publication statusPublished - 2017 Jan 1
Externally publishedYes
Event2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017 - Fukui and Kyoto, Japan
Duration: 2017 Apr 242017 Apr 28

Publication series

Name2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings

Other

Other2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
CountryJapan
CityFukui and Kyoto
Period17/4/2417/4/28

Fingerprint

Zirconium alloys
Pickups
Surface treatment
Steam
Corrosion
Hydrogen
Zirconium
Oxidation
Light water reactors
Accidents
Temperature
Carbon
Exothermic reactions
Spent fuels
Autoclaves
Hydrides
Materials properties
X ray photoelectron spectroscopy
Crystal structure
Annealing

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

Cite this

Furuya, M. (2017). Surface modification technology of fuel cladding, fresh green to mitigate corrosion and hydrogen-pickup in high-temperature steam environment. In 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings (2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings). International Congress on Advances in Nuclear Power Plants, ICAPP.

Surface modification technology of fuel cladding, fresh green to mitigate corrosion and hydrogen-pickup in high-temperature steam environment. / Furuya, Masahiro.

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP, 2017. (2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Furuya, M 2017, Surface modification technology of fuel cladding, fresh green to mitigate corrosion and hydrogen-pickup in high-temperature steam environment. in 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings, International Congress on Advances in Nuclear Power Plants, ICAPP, 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017, Fukui and Kyoto, Japan, 17/4/24.
Furuya M. Surface modification technology of fuel cladding, fresh green to mitigate corrosion and hydrogen-pickup in high-temperature steam environment. In 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP. 2017. (2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings).
Furuya, Masahiro. / Surface modification technology of fuel cladding, fresh green to mitigate corrosion and hydrogen-pickup in high-temperature steam environment. 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP, 2017. (2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings).
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