Aluminum-zircaloy galvanic couple in reactor water

Technical Report · Tue Aug 01 00:00:00 EDT 1978

OSTI ID:6595597

Horton, R M; Miller, R L; Reimann, G A

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; TRN: 78-019687
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
ALUMINIUM
ELECTROCHEMICAL CORROSION
REACTOR MATERIALS
ZIRCALOY 4
CORROSION PROTECTION
EMBRITTLEMENT
HYDRIDATION
PBF REACTOR
WATER COOLED REACTORS
ALLOYS
CHEMICAL REACTIONS
CORROSION
ELEMENTS
METALS
PULSED REACTORS
REACTORS
TANK TYPE REACTORS
TIN ALLOYS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220200* - Nuclear Reactor Technology- Components & Accessories
360105 - Metals & Alloys- Corrosion & Erosion