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. Coquerelle, J. Gabolde, R. Lesser, P. Werner
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 110-119
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31180
Articles are hosted by Taylor and Francis Online.
The European Institute for Transuranium Elements has performed a series of mixed-oxide irradiation experiments in the Dounreay Fast Reactor. The main parameters varied were the O/M ratio of the fuel, radial fuel distribution, and fuel form. Three low burnup experiments with nine pins were terminated in 1969. Eight of the corresponding nine high burnup pins were removed from the reactor subsequently, after several intermediate nondestructive examinations. One pin is further irradiated. Three of the eight pins failed. The Inconel-625 claddings of the sound pins did not change their o.d. at a total neutron dose of 7.3 × 1022 n/cm2. The three pins of the DS-2 experiment, in which fuels with different O/M ratios have been irradiated to a burnup of 7.3 at.%, were examined destructively. A low initial O/M (1.94) led to a negligible attack of the cladding at a maximum temperature of 650°C, whereas fuel of stoichiometric composition corroded severely. No influence of the different O/M on the swelling was detected. The reduction of the O/M ratio to low values seems to increase the risk of central fuel melting.