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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Alireza Haghighat, Maurice A. Robkin
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 503-513
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33175
Articles are hosted by Taylor and Francis Online.
The long-term reduction in potential hazard of geologically stored nuclear wastes achievable by partitioning and transmutation (PT) of the actinides discharged from a mixed-oxide (MOX)-fueled light water reactor coupled to a MOX-fueled liquid-metal fast breeder reactor (LMFBR) is considered for three PT cases:1. 32 cycles of PT with plutonium sent to the repository at every cycle2 .same as item 1 with plutonium sent to the LMFBR as fuel3. PT cycles continued indefinitely.Cross-section and isotope inventory data are taken from the literature for similar facilities and processes and converted to an effective cycle-by-cycle burnup pattern. The effect of PT on potential population hazard into the indefinite future is evaluated on the basis of activity leached from the repository, transported by groundwater, and ingested. The calculation is carried out with two different sets of losses of actinides from facilities, one of which includes very small uranium and plutonium losses. The short-term fatalities expected due to accidents and operational releases are increased up to 67%. The decrease in long-term potential hazard with PT is minimal with the standard loss fractions. In the small loss set, the loss of uranium (which dominates the long-term hazard) is assumed to be very small. The factor of 25 reduction observed in this case is reduced to a factor of 3 when uranium is deleted from the tally. With uranium deleted, both loss fraction sets give the same long-term hazard reduction with PT.