Aluminum-zircaloy galvanic couple in reactor water
The corrosion and hydriding behavior of galvanically coupled 5454 aluminum and zircaloy-4 in a nuclear reactor core was studied in a simulated fuel-cladding/canister configuration. Tests were conducted in reactor quality water at 298 and 355/sup 0/K. Possible control methods by means of protective coatings were also studied. The results indicate that embrittlement of zircaloy-4 by corrosion-induced hydriding would not be a problem in this application, and corrosion damage to the aluminum would not be significant. Findings are applicable for limited periods of service or storage.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6595597
- Report Number(s):
- NUREG/CR-0284; TREE-1169
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
ALUMINIUM
CHEMICAL REACTIONS
CORROSION
CORROSION PROTECTION
ELECTROCHEMICAL CORROSION
ELEMENTS
EMBRITTLEMENT
HYDRIDATION
METALS
PBF REACTOR
PULSED REACTORS
REACTOR MATERIALS
REACTORS
TANK TYPE REACTORS
TIN ALLOYS
WATER COOLED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
ALUMINIUM
CHEMICAL REACTIONS
CORROSION
CORROSION PROTECTION
ELECTROCHEMICAL CORROSION
ELEMENTS
EMBRITTLEMENT
HYDRIDATION
METALS
PBF REACTOR
PULSED REACTORS
REACTOR MATERIALS
REACTORS
TANK TYPE REACTORS
TIN ALLOYS
WATER COOLED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS