ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Takumi Hayashi, Kazuhiro Kobayashi, Yasunori Iwai, Noriko Asanuma, Shigeru O'hira, Masataka F. Nishi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 647-651
Safety and Safety System | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22667
Articles are hosted by Taylor and Francis Online.
In order to demonstrate tritium confinement performance in DT (deuterium-tritium) fusion reactors at any accident, TPL/JAERI has carried out intentional tritium release experiments using Caisson Assembly for Tritium Safety study (CATS). Some data have been accumulated such as actual tritium behavior in the normal ventilated area and response of tritium monitors and emergency isolation valves. The experimental results of confinement of released tritium of about 3 GBq in 12m3 of the Caisson under ventilation of 50 m3/h were consistent with those of simulation by a three dimensional eddy flow calculation code modified from FLOW-3D. Using this simulation code, the tritium confinement performance in large rooms can be demonstrated for actual fusion reactors.