Published June 2016 | Version v1
Journal article Metadata-only

TEM Study of Zircaloy 2 with FeCrAl Layer under Simulated BWR Environment

Creators

  • 1. University of Illinois, Department of Nuclear, Plasma and Radiological Engineering, Urbana, IL 61801 (United States)
  • 2. University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, MI 48109 (United States)

Description

Zircaloy 2 is widely used as nuclear fuel cladding in light-water nuclear reactors, which is resistive to corrosion, creep, and swelling. Due to water chemical reactivity and high-temperature steam exposure, oxidation in zirconium cladding is possible during transients. To mitigate the zirconium oxidation and the hydrogen generation at elevated temperature, we have coated Zircaloy 2 with oxide resistant FeCrAl thin film layers using magnetron sputtering. Transmission electron microscopy (TEM), scanning transmission electron microscopy (STEM), and electron energy-dispersive X-ray spectroscopy (EDX) are used to understand the behavior of the protective FeCrAl layer under typical BWR operation conditions. (authors)

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
114
Journal Issue
1
Journal Page Range
p. 1059-1060
ISSN
0003-018X

Conference

Title
Annual Meeting of the American Nuclear Society. Embedded topical meeting 'Nuclear fuels and structural material for the next generation nuclear reactors'
Dates
12-16 Jun 2016
Place
New Orleans, LA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
52032328
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CLADDING; CORROSION; CREEP; INTERSTITIAL HYDROGEN GENERATION; MAGNETRONS; NUCLEAR FUELS; OXIDATION; SIMULATION; SPUTTERING; SWELLING; THIN FILMS; TRANSMISSION ELECTRON MICROSCOPY; X-RAY SPECTROSCOPY; ZIRCALOY 2; ZIRCONIUM
Descriptors DEC
ALLOYS; ALLOY-ZR98SN-2; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEFORMATION; DEPOSITION; ELECTRON MICROSCOPY; ELECTRON TUBES; ELECTRONIC EQUIPMENT; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EQUIPMENT; FILMS; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; MECHANICAL PROPERTIES; METALS; MICROSCOPY; MICROWAVE EQUIPMENT; MICROWAVE TUBES; NICKEL ADDITIONS; NICKEL ALLOYS; PHYSICAL RADIATION EFFECTS; POWER REACTORS; RADIATION EFFECTS; REACTOR MATERIALS; REACTORS; SPECTROSCOPY; SURFACE COATING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Notes
2 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States