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Title: Reactor Physics Assessment of Alternate Cladding Materials

Authors:
 [1] ;  [1] ;  [1] ;  [1] ;  [1]
  1. ORNL
Publication Date:
OSTI Identifier:
1159474
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 2014 Water Reactor Fuel Performance Meeting/Top Fuel/LWR Fuel Performance Meeting, Sendai, Japan, 20140914, 20140917
Research Org:
Oak Ridge National Laboratory (ORNL)
Sponsoring Org:
NE USDOE - Office of Nuclear Energy
Country of Publication:
United States
Language:
English
Subject:
NUCLEAR FUELS; REACTOR PHYSICS; CLADDING nuclear; nuclear fuel; accident tolerant fuel; ATF; reactor physics; cladding; lattice physics; FeCrAl; SiC; SS304; SS310