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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Latest News
TEPCO releases initial analysis of Fukushima-2 fuel debris sample
Tokyo Electric Power Company has released the results of its initial analysis of a sample of nuclear fuel debris from Unit 2 of Japan’s damaged Fukushima Daiichi nuclear power plant. The sample, which measured around 5mm by 4mm and totaled 0.187 grams, was taken from the floor of the reactor pedestal during a second trial removal of fuel debris conducted in April.
Gilles J. Youinou
Nuclear Technology | Volume 198 | Number 2 | May 2017 | Pages 202-216
Technical Paper | doi.org/10.1080/00295450.2017.1305191
Articles are hosted by Taylor and Francis Online.
This paper presents the results of a neutronics analysis related to the homogeneous recycling of different mixtures of transuranic elements (transuranics) (TRU) in pressurized water reactors (PWRs) loaded with mixed oxide (MOX) fuel using enriched uranium instead of depleted uranium (UenrO2-TRUO2, i.e., MOX-EU). It also addresses an often, if not always, overlooked aspect related to the recycling of TRU in PWRs, namely, the use of reprocessed uranium. From a neutronics point of view, it is possible to multirecycle the entirety of the plutonium with or without neptunium and americium in a PWR fleet using MOX-EU fuel in between one-third and two-thirds of the fleet. Recycling neptunium and americium with plutonium significantly decreases the decay heat of the waste stream between 100 to 1000 years compared to that of an open fuel cycle or when only plutonium is recycled. The uranium present in MOX-EU used fuel still contains a significant amount of 235U, and recycling it makes a major difference in the natural uranium needs. For example, at equilibrium, a PWR fleet recycling its plutonium, neptunium, and americium in MOX-EU needs 28% more natural uranium than a reference UO2 open cycle fleet generating the same energy if the reprocessed uranium is not recycled and 19% less if the reprocessed uranium is recycled back in the reactors, i.e., a 47% difference. Reenriching the reprocessed uranium is not necessary.