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Title: Tritium Behavior in Zircaloy Cladding from Used Light Water Reactor Fuel Rods

Authors:
 [1] ;  [1] ;  [2]
  1. ORNL
  2. {Joe} M [ORNL
Publication Date:
OSTI Identifier:
1156719
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: WM Symposia 2014, Phoenix, AZ, USA, 20140302, 20140302
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