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Title: AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding

Journal Article · · Arab Gulf Journal of Scientific Research (1989)
 [1]; ORCiD logo [1];  [1];  [2];  [3];  [3];  [4];  [5];  [5];  [6];  [7]
  1. AREVA NP-Fuel Design, Lyon (France)
  2. AREVA NP-Component Research Center, Ugine (France)
  3. AREVA NP-Le Creusot Technical Center, Le Creusot (France)
  4. AREVA NP-Fuel Manufacturing, Romans-sur-Isere (France)
  5. Univ. Paris-Saclay, Gif-sur-Yvette (France); Alternative Energies and Atomic Energy Commission (CEA), Gif-sur-Yvette (France)
  6. AREVA NP GmbH-Fuel Design, Erlangen (Germany)
  7. 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
Citation Metrics:
Cited by: 143 works
Citation information provided by
Web of Science

References (6)

Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4 journal December 2015
Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding journal November 2015
Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding journal September 2016
Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea journal February 2016
Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating journal October 2015
Microstructure and Oxidation Behavior of CrAl Laser-Coated Zircaloy-4 Alloy journal February 2017

Cited By (4)

Hydrogen Interaction with Deep Surface Modified Zr-1Nb Alloy by High Intensity Ti Ion Implantation 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

Figures / Tables (7)