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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
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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Latest News
Kentucky legislature sends nuclear bills to governor
Kentucky’s Republican-majority legislature passed a bill this past week that could bring nuclear energy to the “coal-is-king” state as lawmakers broadly seek solutions to reduce carbon emissions. The bill went to Democratic Gov. Andrew Beshear on Monday for final approval.
Jack Galloway, Cetin Unal
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 523-537
Technical Paper | doi.org/10.13182/NSE15-7
Articles are hosted by Taylor and Francis Online.
While Zircaloy-based claddings have been the workhorse for the nuclear power industry for decades, they have also demonstrated problems, particularly regarding accident scenarios. Work has been performed to assess the viability of stainless steel–based cladding in traditional light water reactors. This paper assesses the reactivity penalty of moving to stainless steel cladding using Monteburns, while attempting to minimize this penalty by increasing the fuel pellet radius and decreasing the cladding thickness. Fuel performance simulations using BISON have also been performed to quantify gains or losses in structural integrity when moving to thinner, stainless steel claddings. Thermal and irradiation creep, along with fission gas swelling, thermal swelling, and fuel relocation, are accounted for in the models for both Zircaloy and stainless steel claddings. Additional models for the lower-oxidation stainless steel APMT are also invoked where available, with irradiation data for HT9 used as a fallback in the absence of appropriate models. In this study the isotopic vectors within each natural element are varied to assess potential reactivity gains if advanced enrichment capabilities were levied toward cladding technologies. Recommendations on cladding thicknesses for a robust cladding as well as the constitutive components of a less penalizing composition are provided.