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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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August 2024
Nuclear Technology
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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.
P. Greebler, B. A. Hutchins, R. B. Linford
Nuclear Technology | Volume 4 | Number 5 | May 1968 | Pages 297-306
Technical Paper and Note | doi.org/10.13182/NT68-A26395
Articles are hosted by Taylor and Francis Online.
The uncertainties in physics parameters and in fuel cost of fast power reactors due to current nuclear data uncertainties are considered for two sodium-cooled, oxide-fueled, 1000 MW(e) reactors. One reactor has a low core neutron leakage and a core composition that results in very low fuel cost and short doubling time for fissile material. The second reactor is forced to satisfy stringent safety criteria associated with the sodium voiding reactivity problem and, hence, has a high core neutron leakage and a large amount of moderating material (BeO) in its core composition, with resultant higher fuel cost. Ranges in uncertainties in fuel cost and doubling time for each recognized significant data uncertainty over a “correlated” energy interval are evaluated for each of the two reactors, using the highest and the lowest reasonable values of that nuclear data parameter, as well as the values recommended in the Brookhaven Evaluated Nuclear Data Files (ENDF/B). Combined uncertainties in data produce an uncertainty of ∼0.15 mill/kWh in fuel cost for the low leakage reactor and 0.25 mill/kWh for the reactor for which the design composition (BeO content) must be adjusted as the nuclear data are varied, in order to satisfy the stringent sodium voiding safety criteria. The current large uncertainty in the value of α for 239Pu below 15 keV is the largest single contributor to this overall fuel cost uncertainty, closely followed by the uncertainties in for 239Pu and σc(σc = σn,y) for 238U. On the basis of the calculated sensitivity of fuel cost to specific data uncertainties, a set of targets for nuclear data accuracy that would reduce the calculated fuel cost uncertainty to about ±0.03 mill/kWh is recommended.