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
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
L. W. Lang
Nuclear Technology | Volume 9 | Number 2 | August 1970 | Pages 242-249
Economic | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28813
Articles are hosted by Taylor and Francis Online.
The power costs of three hypothetical reactor sites are analyzed to compare the site costs of conventionally fueled fast and thermal reactors with thorium-blanketed breeders and 233U fueled light-water reactors (LWR's). Since the most critical parameter is time, three case variations are considered. The site start-up is considered coincident with the commercial introduction of the fast reactor; and alternatively, where site start-up occurs jive and ten years after the commercial introduction of the breeder. The cost comparisons also consider the effect of U3O8 price increases. The value of 233U produced by thorium-blanketed breeders exceeds that of the Pu produced by 238U blanketed breeders. Since the power costs of the LWR's are lower than the breeders until the price of U3O8 increases, early development of the breeders may be contingent upon implementation of the crossed-progeny fueling.