Tritium Content in and Release from Pressurized Water Reactor Fuel Cladding
Conference
·
OSTI ID:1324073
- ORNL
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1324073
- Resource Relation:
- Conference: 2016 ANS Annual Meeting, New Orleans, LA, USA, 20160612, 20160612
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of Tritium Content and Release from Pressurized Water Reactor Fuel Cladding
Tritium Content in and Release from Pressurized-Water-Reactor Fuel Cladding
Tritium Behavior in Zircaloy Cladding from Used Light Water Reactor Fuel Rods
Technical Report
·
Tue Sep 01 00:00:00 EDT 2015
·
OSTI ID:1324073
+1 more
Tritium Content in and Release from Pressurized-Water-Reactor Fuel Cladding
Journal Article
·
Wed Jun 15 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:1324073
+1 more
Tritium Behavior in Zircaloy Cladding from Used Light Water Reactor Fuel Rods
Conference
·
Wed Jan 01 00:00:00 EST 2014
·
OSTI ID:1324073