학술논문

Spot weld attachment of thermocouples to a fuel rod cladding interior surface
Document Type
Technical Report
Author
Source
Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
Subject
22 GENERAL STUDIES OF NUCLEAR REACTORS FUEL CANS
THERMOCOUPLES
WELDING
WATER COOLED REACTORS
ZIRCALOY 4
ALLOYS
FABRICATION
JOINING
MEASURING INSTRUMENTS
REACTORS
TIN ALLOYS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS 220300* -- Nuclear Reactor Technology-- Fuel Elements
Language
English
Abstract
Research was conducted by Pacific Northwest Laboratory to weld 0.020-inch-diameter thermocouples to the interior surface of Zircaloy 4 light-water reactor fuel cladding. Inconel sheathed Type K thermocouples were attached to fuel cladding to register cladding temperatures during loss-of-coolant accident testing. This report describes the development of welding parameters and the effects of thermocouple attachment on the burst strength and integrity of the cladding at temperatures up to 1550/sup 0/F.