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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
C. E. Sessions, S. D. Reynolds, Jr., M. A. Hebbar, J. F. Lewis, J. H. Kiefer
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 270-279
Technical Paper | Materials | doi.org/10.13182/NT55-270
Articles are hosted by Taylor and Francis Online.
The progress achieved since 1977 in the important area of materials and processes development of fast reactor steam generator development is summarized. The two distinguishing features of the proposed Westinghouse-Tampa steam generator concept are the convoluted shell expansion joint (CSEJ) and the double-wall tubing with a third fluid leak detection capability. A Cr—1 Mo low alloy steel will be used for all important parts of the generator including the CSEJ and the tubes. Other areas in which progress was made include tube-to-tubesheet (TITS) welding, post-weld heat treatment (PWHT), tube expansion, and development of materials specifications for prototype and future plant materials. The tubing development work was based on the successful completion of a manufacturing feasibility program in 1974. This activity has involved manufacture of 23.47-m (77-ft)-long pre-stressed double-wall tubing (DWT) and testing of the tubing for dimensional tolerance or control interface residual stress, heat transfer, interface wear, and gas flow rates at the DWT interface. Results illustrate the capabilities of the vendors’ tube manufacturing process in achieving the important attributes of a leak detecting, prestressed, double-wall steam generator concept. The CSEJ material selection and design have evolved significantly since 1977. A materials change from Alloy 600 to Cr—1 Mo was recently made. The approach to manufacturing the CSEJ is to machine the convolutes from a large pre-forged ring of remelt Cr—1 Mo steel. Significant welding and PWHT process development progress has been achieved for both accessible and inaccessible T/TS welds. Equipment has been designed and manufactured successfully, and welding parameter development is well under way. Automatic and manual welding guns utilizing the pulsed current technique are described. The approach to PWHT involves induction heating for short times at a relatively high tempering temperature. Temperature control of the induction unit involves a preprogrammed heating cycle and feedback control using infrared sensors or thermocouples.