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.
M. J. Bell
Nuclear Technology | Volume 18 | Number 1 | April 1973 | Pages 5-14
Technical Paper | Fuel | doi.org/10.13182/NT73-A16102
Articles are hosted by Taylor and Francis Online.
The ORIGEN computer code has been used to compute the time-dependent thermal power, photon spectrum, and neutron production rate resulting from fast- and thermal-neutron-induced fission of 235U and 239Pu fuels. Computed afterheats and photon spectra of fission products resulting from thermal fission of 235U are shown to be in good agreement with published data, and computed radioactivities and thermal power of plutonium irradiated to low exposures in both thermal- and fast-neutron spectra are found to agree well with experimentally measured properties. Radioactive decay of the actinide elements is calculated to contribute 10 to 25% of the thermal power of spent low enrichment 235U fuels at postirradiation times between one day and three years. Gamma radiation per unit mass of 30-day-cooled LMFBR core fuel is calculated to exceed that from 90-day-cooled PWR fuel by a factor of 30 in the higher energy groups, and spontaneous fission neutron production per gram of spent LMFBR core fuel is found to exceed that of PWR fuel by a factor of 3 at these times.