skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Early implementation of SiC cladding fuel performance models in BISON

Technical Report ·
DOI:https://doi.org/10.2172/1215605· OSTI ID:1215605
 [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

SiC-based ceramic matrix composites (CMCs) [5–8] are being developed and evaluated internationally as potential LWR cladding options. These development activities include interests within both the DOE-NE LWR Sustainability (LWRS) Program and the DOE-NE Advanced Fuels Campaign. The LWRS Program considers SiC ceramic matrix composites (CMCs) as offering potentially revolutionary gains as a cladding material, with possible benefits including more efficient normal operating conditions and higher safety margins under accident conditions [9]. Within the Advanced Fuels Campaign, SiC-based composites are a candidate ATF cladding material that could achieve several goals, such as reducing the rates of heat and hydrogen generation due to lower cladding oxidation rates in HT steam [10]. This work focuses on the application of SiC cladding as an ATF cladding material in PWRs, but these work efforts also support the general development and assessment of SiC as an LWR cladding material in a much broader sense.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1215605
Report Number(s):
ORNL/TM-2015/452; AF5810000; NEAF278
Country of Publication:
United States
Language:
English

Similar Records

SiC-CMC-Zircaloy-4 Nuclear Fuel Cladding Performance during 4-Point Tubular Bend Testing
Conference · Sun Sep 01 00:00:00 EDT 2013 · OSTI ID:1215605

Chromium-Based Mitigation Coatings on SiC Materials for Fuel Cladding
Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1215605

Development of SiC-based Cladding for Accident Tolerant Fuels
Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1215605