Initial Evaluation of the Heat-Affected Zone, Local Embrittlement Phenomenon as it Applies to Nuclear Reactor Vessels | Zendy

D.E. McCabe | Zendy

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Initial Evaluation of the Heat-Affected Zone, Local Embrittlement Phenomenon as it Applies to Nuclear Reactor Vessels

Author(s) -

D.E. McCabe

Publication year - 1999

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/12551

Subject(s) - embrittlement , reactor pressure vessel , pressure vessel , submarine pipeline , materials science , heat affected zone , brittleness , nuclear engineering , metallurgy , welding , geology , geotechnical engineering , engineering , composite material

The objective of this project was to determine if the local brittle zone (LBZ) problem, encountered in the testing of the heat-affected zone (HAZ) part of welds in offshore platform construction, can also be found in reactor pressure vessel (RPV) welds. Both structures have multipass welds and grain coarsening along the fusion line. Literature was obtained that described the metallurgical evidence and the type of research work performed on offshore structure welds

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