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Title: Material selection for accident tolerant fuel cladding

Alternative cladding materials are being investigated for accident tolerance, which can be defined as >100X improvement (compared to current Zr-based alloys) in oxidation resistance in steam environments at ≥1200°C for short (≤4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800°C could not be reproduced. Both FeCrAl and MAX phase Ti 2AlC form a protective alumina scale in steam. Therefore, commercial Ti 2AlC that is not single phase, formed a much thicker oxide at 1200°C in steam and significant TiO 2, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475°C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich α’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated.
 [1] ;  [1] ;  [1] ;  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Report Number(s):
Journal ID: ISSN 2196-2936; TRN: US1600460
Grant/Contract Number:
Accepted Manuscript
Journal Name:
Metallurgical and Materials Transactions. E, Materials for Energy Systems
Additional Journal Information:
Journal Volume: 2; Journal Issue: 3; Journal ID: ISSN 2196-2936
ASM International
Research Org:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
Country of Publication:
United States
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; accident tolerant LWR Fuel cladding; FeCrAl; Mo; Ti2AlC; Al2O3; high temperature steam oxidation resistance; LOCA; MAX phase
OSTI Identifier: