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Title: PREDICTIVE MODEL FOR CHRONIC OXIDATION OF NUCLEAR GRAPHITE UNDER NORMAL OPERATING CONDITIONS OF HIGH TEMPERATURE GAS-COOLED REACTORS

Authors:
 [1] ;  [2] ;  [3] ;  [1] ;  [1] ;  [3]
  1. ORNL
  2. University of Tennessee (UT)
  3. Idaho National Laboratory (INL)
Publication Date:
OSTI Identifier:
1286982
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: CARBON 2016 - The World Conference on Carbon, State College, PA, USA, 20160710, 20160715
Research Org:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
ORNL work for others
Country of Publication:
United States
Language:
English
Subject:
graphite; high temperature gas-cooled reactors; HTGR; moisture; oxidation