The propagation of zirconium runaway oxidation of spent fuel cladding following loss of water during storage
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.
Main Author: | Pisano, Nicola Anthony |
---|---|
Other Authors: | Frederick Best. |
Format: | Thesis |
Language: | eng |
Published: |
Massachusetts Institute of Technology
2011
|
Subjects: | |
Online Access: | http://hdl.handle.net/1721.1/64837 |
Similar Items
-
Quality assurance and control in the manufacture of metal-clad UO2 reactor fuels /
by: 7924 International Atomic Energy Agency -
Electrochemical Formation of Hydride Phases on the Zirconium- 1% Niobium Alloy Used in Nuclear Fuel Cladding
by: I Moradi Gharatloo, et al.
Published: (2016-08-01) -
Dynamic Charge Carrier Transport Behaviors in Zirconium Oxide for Nuclear Cladding Materials
by: Il-Kyu Park, et al.
Published: (2020-07-01) -
The impact of large-grained UO2 pellet and coated zirconium cladding on design criteria for PWR fuel rod
by: YOU Yan, et al.
Published: (2021-11-01) -
Subcritical crack growth in zirconium alloys
by: Paes de Andrade, Arnaldo Homobono
Published: (2005)