Development of compressive residual stresses in underwater PTA welds

Z. Feng, R. A. White, E. Willis, H. D. Solomon

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

1 Scopus citations

Abstract

The repair of nuclear reactor internals can generally best be done underwater to take advantage of the shielding that the water provides, and to eliminate the need to remove the fuel. These advantages prompted a study of underwater plasma transfer arc (PTA) welding. It was found that there was actually a benefit to performing the welding underwater. Rather than the typical tensile residual stresses that are developed in the weld and heat affected zone, HAZ, (which promotes stress corrosion cracking, SCC, and corrosion fatigue), the underwater welds exhibited compressive stresses, or at least greatly reduced tensile stresses. This paper aims at explaining why this is the case. Welding under water produces a significant difference in the temperature distribution. In conventional welding the poor heat conduction out from the face of the plate being welded, results in the surface being hot relative to the interior of the plate. Welding underwater reverses this gradient because of the good heat conduction into the water. This temperature distribution difference is modeled using finite element analysis, FEA, and is used to demonstrate, through FEA, why these compressive stresses develop.

Original languageEnglish
Title of host publicationProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
EditorsS. Bruemmer, P. Ford, G. Was
PublisherMinerals, Metals and Materials Society
Pages757-766
Number of pages10
ISBN (Print)0873394755, 9780873394758
DOIs
StatePublished - 1999
EventProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - - New Portbeach, CA, United States
Duration: Aug 1 1999Aug 5 1999

Publication series

NameProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Conference

ConferenceProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
Country/TerritoryUnited States
CityNew Portbeach, CA
Period08/1/9908/5/99

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