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Division Spotlight
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.
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?
A. Alberman, G. Bley, P. Pépin, P. Soulat
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 639-646
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33485
Articles are hosted by Taylor and Francis Online.
Within the framework of the high-temperature gas-cooled reactor (HTGR) R&D agreement with GA Technologies, Inc., the Centre d’Etudes Nucléaires de Saclay investigated the transition temperature shift of the liner steel exposed to (thermal) neutrons. The steel was ferritic A537 (1.32% manganese, 0.26% copper, 0.26% silicon, 0.21% nickel, and 0.14% chromium). The specimens were irradiated in the French EL3 heavy water research reactor in an area where the neutron spectrum was comparable to that occurring in front of the HTGR core cavity liner:Φth/Φƒ ∼ 1000 . The temperature was 60 °C during the irradiations. For theoretical purposes, two irradiations were carried out at two different fluences. In addition, some specimens were cadmium plated to examine the effect of fast neutrons. Charpy impact tests were performed at Saclay with an instrumented impact device. The results show that current models overestimate the thermal neutron effect by a factor of 3.
