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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
W. F. Naughton, M. J. Cenko, S. H. Levine, W. F. Witzig
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 256-272
Technical Paper | Fuel | doi.org/10.13182/NT74-A15918
Articles are hosted by Taylor and Francis Online.
A core management program has been effected for TRIGA reactors (TRICOM) which utilizes three basic types of information: (a) keff as a function of burnup, (b) relative changes in power fractions of fuel elements as a function of core burnup, and (c) reactivity worth curves for fissile isotopes and neutron absorbers. TRICOM has been programmed for an IBM system/360 using the FORTRAN IV language. Experimental measurements have been made with 8.5 wt% uranium and a mixture of 8.5 and 12 wt% uranium-fueled cores, and the results have been compared with those calculated by TRICOM. The analytical and experimental results compare favorably in all cases, particularly when some of the experimentally measured parameters are substituted for those derived theoretically. A significant result of this study program has been the development of an improved refueling scheme for The Pennsylvania State University’s Breazeale Nuclear Reactor which replaces depleted 8.5 wt% fuel with 12 wt% uranium fuel.