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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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?
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 630-638
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33484
Articles are hosted by Taylor and Francis Online.
The effect of neutron irradiation on hightemperature tensile and creep properties of austenitic heat-resistant alloys was studied. The effect, which appeared in the loss of ductility at elevated temperatures, was caused by helium produced by a nuclear transmutation reaction of thermal neutrons with boron and nickel in the alloy. The fracture mode was characterized by intergranular cracking. The tensile properties were determined at 700 to 1000°C after irradiation up to a maximum thermal neutron fluence of 1.2 x 1025 n/m2. Creep tests were made at 900°C after irradiation to 6.6 x 1024 and 7.5 x 1024 n/m2. The tensile ductility was reduced with increasing deformation temperature, due primarily to the loss of necking elongation. In the postirradiation creep tests, significant reduction in rupture life also occurred. In both tensile and creep properties, the iron-base alloys were superior to the nickel-rich alloys, and, in particular, a heat of Incoloy alloy 800 showed exceptionally high resistance to irradiation.