The impact of Materials and Processes (M and P) development activities at the Nuclear Components Division - Breeder Reactor Components Project of Westinghouse are described. Nine specific M and P programs have been performed over the past five years and the conclusions drawn from each are summarized herein. These engineering activities could be classified as component design, fabrication, and testing results. However, the discussion presented is from a materials engineer’s viewpoint as to how the previously proposed development tasks have answered existing questions about either design, manufacturing, or plant operation. The nine areas which are discussed include (i) double-wall tubing, (ii) tube-to-tubesheet welding, (iii) few tube model fabrication and testing, (iv) tube support plates, (v) shell welding, (vi) convoluted shell expansion joint, (vii) water chemistry and corrosion behavior, (viii) chemical cleaning, and (ix) surface contamination protection.
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October 1983
This article was originally published in
Journal of Engineering for Power
Research Papers
LMFBR Steam Generator Materials Development at Westinghouse
M. A. Hebbar
,
M. A. Hebbar
Breeder Reactor Components Project, Westinghouse Nuclear Components Division, Tampa, Fla.
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C. E. Sessions
C. E. Sessions
Breeder Reactor Components Project, Westinghouse Nuclear Components Division, Tampa, Fla.
Search for other works by this author on:
M. A. Hebbar
Breeder Reactor Components Project, Westinghouse Nuclear Components Division, Tampa, Fla.
C. E. Sessions
Breeder Reactor Components Project, Westinghouse Nuclear Components Division, Tampa, Fla.
J. Eng. Power. Oct 1983, 105(4): 719-725 (7 pages)
Published Online: October 1, 1983
Article history
Received:
July 23, 1982
Online:
September 28, 2009
Citation
Hebbar, M. A., and Sessions, C. E. (October 1, 1983). "LMFBR Steam Generator Materials Development at Westinghouse." ASME. J. Eng. Power. October 1983; 105(4): 719–725. https://doi.org/10.1115/1.3227473
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