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Title: WELDING DEVELOPMENT FOR FBR STAINLESS STEEL COMPONENTS.

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., Tenn.
OSTI Identifier:
4724945
Report Number(s):
ORNL-TM-3300
NSA Number:
NSA-25-049372
Resource Type:
Technical Report
Resource Relation:
Other Information: In Fuels and materials development program. UNCL. Orig. Receipt Date: 31-DEC-71
Country of Publication:
United States
Language:
English
Subject:
N30120* -Metals, Ceramics, & Other Materials-Metals & Alloys-Preparation & Fabrication; N38700 -Reactor Components, Fuels & Accessories; AUSTENITE; HEAT TREATMENTS; IRRADIATION; LMFBR; MECHANICAL PROPERTIES; NEUTRONS; PRESSURE VESSELS; RADIATION EFFECTS; STAINLESS STEELS; TESTING; WELDS; WELDING/methods for LMFBR component, development of; STAINLESS STEEL/mechanical properties of welds in austenitic, effects of fabrication methods on; STAINLESS STEEL/radiation effects on welds of austenitic, relations of heat treatments with neutron; NEUTRONS/effects on stainless steel welds, relations with heat treatments

Citation Formats

Weir, Jr, J R, Slaughter, G M, and Goodwin, G M. WELDING DEVELOPMENT FOR FBR STAINLESS STEEL COMPONENTS.. United States: N. p., 1971. Web. doi:10.2172/4724945.
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Weir, Jr, J R, Slaughter, G M, & Goodwin, G M. WELDING DEVELOPMENT FOR FBR STAINLESS STEEL COMPONENTS.. United States. doi:10.2172/4724945.
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Weir, Jr, J R, Slaughter, G M, and Goodwin, G M. Sun . "WELDING DEVELOPMENT FOR FBR STAINLESS STEEL COMPONENTS.". United States. doi:10.2172/4724945. https://www.osti.gov/servlets/purl/4724945.
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@article{osti_4724945,
title = {WELDING DEVELOPMENT FOR FBR STAINLESS STEEL COMPONENTS.},
author = {Weir, Jr, J R and Slaughter, G M and Goodwin, G M},
abstractNote = {},
doi = {10.2172/4724945},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Oct 31 00:00:00 EDT 1971},
month = {Sun Oct 31 00:00:00 EDT 1971}
}
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Technical Report:
View Technical Report (0.74 MB)
DOI:  10.2172/4724945
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    In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tubesheets to ASTM Specification A350-Grade LF-1, modifled with 1.66% nickel; and weld the tube ends to the stainless steel overlay previously applied to the tubesheet. The rolled joint was a necessary precaution to prevent secondary water, that might contain chlorides, from contacting the stainless steel weld joining the tubes to the tubesheets. The welded joint provided the mechanical strength for attaching the tubes to the tubesheets. A laboratory program was conducted, therefore, to develop practicable procedures for weldingmore » the Type 430M tubes to the stainless steel overlay; as well as to assure that the tubes could satisfactorily be rolled to the tubesheets. Automatic and manual tungstenare welding procedures were developed that were capable of consistently providing an austenitic weld having a strength exceeding that of the heat affected zone or the unaffected tube itself. Type 430M tubes in the asreceived, and softened conditions were rolled into prototype test units under various conditions of rolling. It was concluded that the Type 450M tubes in the as-received condition could be satisfactorily rolled into the A360Grade LF-1 tubesheet and be tlght to a pressurized helium leak test. To translate the laboratory procedures into fabrication practice for the steam generator consisting of the same materials, detailed welding and rolling procedures were outlined and transmitted to the fabricator, as well as included in this report. (auth)« less

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