Investigations of Aluminum-Doped Self-Healing Zircaloy Surfaces in Context of Accident-Tolerant Fuel Cladding Research
We present here some important results investigating aluminum as an effective surface dopant for increased oxidation resistance of zircaloy nuclear fuel cladding. At first, the transport behavior of aluminum into reactor grade zircaloy was studied using simple diffusion couples at temperatures great...
Main Authors: | Carr, James, Vasudevamurthy, Gokul, Hinderliter, Brian, Massey, Caleb, Snead, Lance |
---|---|
Other Authors: | MIT Nuclear Reactor Laboratory |
Format: | Article |
Language: | English |
Published: |
Springer US
2016
|
Online Access: | http://hdl.handle.net/1721.1/105854 |
Similar Items
-
Hydrogen entry in Zircaloy-4 fuel cladding : an electrochemical study
by: Jarvis, Jennifer Anne
Published: (2016) -
Wettability of candidate Accident Tolerant Fuel (ATF) cladding materials in LWR conditions
by: Jena, Anupam,S.M.Massachusetts Institute of Technology.
Published: (2020) -
Estimation of coping time in pressurized water reactors for accident tolerant fuel claddings
by: Gurgen, Anil
Published: (2018) -
Impact of reactor environment on quenching heat transfer of accident tolerant fuel cladding
by: Seshadri, Arunkumar.
Published: (2019) -
Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance
by: Champagne, Victor, et al.
Published: (2018)