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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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?
M. G. Robin
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 482-489
Technical Paper | Reactor | doi.org/10.13182/NT76-A31528
Articles are hosted by Taylor and Francis Online.
The Stein Industrie steam generator of the 250-MW(e) demonstration fast breeder reactor Phenix comprises three units. Each unit is divided into 12 evaporator modules, 12 superheater modules, and 12 reheater modules. Twenty-four evaporators are made of 2¼ Cr—1 Mo ferritic steel and 12 are made of 2¼ Cr—1 Mo—1 Nb stabilized ferritic steel. All superheaters and reheaters are made of 321 austenitic steel. Since Oct. 1973, this steam generator has been submitted to a number of startups and shutdowns and some 9000 h of operation at full load without any leak, with an acceptable hydrogen diffusion rate of 0.25 g/h per unit through the single wall of the tubes. The Fives-Cail Babcock steam generator selected for the 1200-MW(e) Fast Breeder Power Plant Super Phenix is comprised of four modules with a 357-tube helical bundle made of Alloy 800 housed in a shell made of an austenitic steel (Type 304 or 316L). The module is rated at 750 MW(th) and weighs 140 tons. Other steam generators made of ferritic steels are considered in the longer range for power plants beyond Super Phenix.