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Division Spotlight
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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Jan 2025
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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
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?
A. E. Pickett, W. L. Pearl, M. C. Rowland
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 453-461
Technical Paper | doi.org/10.13182/NT65-A20557
Articles are hosted by Taylor and Francis Online.
Nonsensitized Type-304 stainless-steel fuel cladding cracked intergranularly when exposed to high-temperature, high-purity, water reactor environments. Similar failures were produced out of reactor in stressed tubular-capsule specimens exposed to dilute solutions of iron chloride, copper chloride, sodium hydroxide, and chromic acid at 650° F (343°C). An iron chloride test was developed that closely simulates the intergranular attack on stressed nonsensitized Type-304 stainless-steel fuel cladding. Stressed, cold-worked, nonsensitized Type-304 stainless-steel tubing cracked in less than 24 h at 650° F when exposed to ferric-ferrous chloride solutions containing only 40 Cl parts/106 and 4 soluble-iron parts/106. Exposure at 650° F caused intergranular cracking only, while exposure at 550° F (288° C) caused mixed transgranular and intergranular cracking. The accelerated autoclave test can be used for screening of prospective cladding materials and alloy modifications and developing a better understanding of the mechanism of attack.
