skip to main content

Title: Tritium Content in and Release from Pressurized Water Reactor Fuel Cladding

Authors:
 [1] ;  [1] ;  [2] ;  [1]
  1. ORNL
  2. {Joe} M [ORNL
Publication Date:
OSTI Identifier:
1324073
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 2016 ANS Annual Meeting, New Orleans, LA, USA, 20160612, 20160612
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