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Title: Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors

Authors:
 [1]
  1. ORNL
Publication Date:
OSTI Identifier:
1252151
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, USA, 20160417, 20160420
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; HTGR; gas reactor; FCM; fully ceramic microencapsulated; graphite; SiC; silicon carbide; advanced reactor; nuclear reactor; high-temperature gas-cooled reactor; depletion