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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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.
