Published August 1978 | Version v1
Report Restricted

Aluminum-zircaloy galvanic couple in reactor water

Creators

Description

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 3550K. 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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
101 p.
Report number
NUREG/CR--0284

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10437928
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
Descriptors DEI
ALUMINIUM; CORROSION PROTECTION; ELECTROCHEMICAL CORROSION; EMBRITTLEMENT; HYDRIDATION; PBF REACTOR; REACTOR MATERIALS; WATER COOLED REACTORS; ZIRCALOY 4
Descriptors DEC
ALLOYS; CHEMICAL REACTIONS; CORROSION; ELEMENTS; METALS; PULSED REACTORS; REACTORS; TANK TYPE REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Secondary number(s)
TREE--1169.