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Title: Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors

Authors:
 [1] ;  [1] ;  [1] ;  [1]
  1. ORNL
Publication Date:
OSTI Identifier:
1185572
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 2014 American Nuclear Society (ANS) Winter Meeting and Nuclear Technology Expo, Anaheim, CA, USA, 20141109, 20141113
Research Org:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
NE USDOE - Office of Nuclear Energy
Country of Publication:
United States
Language:
English
Subject:
nuclear; nuclear fuel; accident tolerant fuel; ATF; reactor physics; cladding; FeCrAl; SiC; PWR; BWR; pressurized water reactor; boiling water reactor