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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 Technology
Fusion Science and Technology
February 2024
Latest News
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
A. I. Markin, E. A. Azizov, N. I. Siromyatnikov, V. E. Cherkovets, L. A. Rivkis, A. A. Semenov, I. G. Prikina
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 489-492
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1860
Articles are hosted by Taylor and Francis Online.
The investigations of the tritium distribution in a surface layer and in the depth of samples using a magnetic microscope were carried out. The dependence of a saturation level in the boundary layer for hydrogen was established from a preliminary examination of samples. Conservation of the tritium distribution profile in the depth of the stainless steel samples after completion of their saturation and cooling was assigned. For Inconel-625 substantial tritium redistribution and release during storage (300K, 15 and 28 months) were experimentally ascertained to a greater degree satisfies the classical characteristics of the diffusion process. The "braking" effect of tritium diffusion was found by preliminary saturation of samples by hydrogen. Research in tritium decontamination effects for samples saturated with tritium with various technological preparation was carried out and essential increase of its efficiency was founded. The experiments emulated a model of technological operation cycle of the thermonuclear reactor.