AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding
- AREVA NP-Fuel Design, Lyon (France)
- AREVA NP-Component Research Center, Ugine (France)
- AREVA NP-Le Creusot Technical Center, Le Creusot (France)
- AREVA NP-Fuel Manufacturing, Romans-sur-Isere (France)
- Univ. Paris-Saclay, Gif-sur-Yvette (France); Alternative Energies and Atomic Energy Commission (CEA), Gif-sur-Yvette (France)
- AREVA NP GmbH-Fuel Design, Erlangen (Germany)
- AREVA Inc.-Fuel Design, Lynchburg, VA (United States)
AREVA NP (Courbevoie, Paris, France) is actively developing several enhanced accident-tolerant fuels cladding concepts ranging from near-term evolutionary (Cr-coated zirconium alloy cladding) to longterm revolutionary (SiC/SiC composite cladding) solutions, relying on its worldwide teams and partnerships, with programs and irradiations planned both in Europe and the United States. The most advanced and mature solution is a dense, adherent chromium coating on zirconium alloy cladding, which was initially developed along with the CEA and EDF in the French joint nuclear R&D program. The evaluation of the out-of-pile behavior of the Cr-coated cladding showed excellent results, suggesting enhanced reliability, enhanced operational flexibility, and improved economics in normal operating conditions. For example, because chromium is harder than zirconium, the Cr coating provides the cladding with a significantly improved wear resistance. Furthermore, Cr-coated samples exhibit extremely low corrosion kinetics in autoclave and prevents accelerated corrosion in harsh environments such as in water with 70 ppm Li leading to improved operational flexibility. Finally, AREVA NP has fabricated a physical vapor deposition prototype machine to coat full-length cladding tubes. This machine will be used for the manufacturing of full-length lead test rods in commercial reactors by 2019.
- Research Organization:
- Framatome, Inc., Charlotte, NC (United States); AREVA Inc., Lynchburg, VA (United States). Fuel Design
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- Grant/Contract Number:
- NE0008220
- OSTI ID:
- 1632989
- Alternate ID(s):
- OSTI ID: 1501539
- Journal Information:
- Arab Gulf Journal of Scientific Research (1989), Vol. 50, Issue 2; ISSN 1738-5733
- Publisher:
- Korean Nuclear SocietyCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
Hydrogen Interaction with Deep Surface Modified Zr-1Nb Alloy by High Intensity Ti Ion Implantation
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journal | December 2018 |
Oxidation behavior of RF magnetron sputtered Cr–SiC–Cr composites coating on zircaloy fuel cladding
|
journal | July 2019 |
Atomic-scale interface structure of a Cr-coated Zircaloy-4 material
|
journal | April 2018 |
Scale up of a DLI-MOCVD process for the internal treatment of a batch of 16 nuclear fuel cladding segments with a CrCx protective coating
|
journal | October 2019 |
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