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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.
J. Greenborg
Nuclear Technology | Volume 2 | Number 5 | October 1966 | Pages 430-439
Technical Paper and Note | doi.org/10.13182/NT66-A27621
Articles are hosted by Taylor and Francis Online.
Extensive neutron and gamma-ray measurements were performed in the reflector and primary shield of the NPR, a large power and plutonium production reactor. The measurements yielded fast, epithermal, and thermal-neutron flux and gamma-ray dose distributions through approximately 9 ft of reflector and shield assembly. Emphasis was placed on obtaining absolute flux and dose measurements with respect to reactor power. The measured fluxes and dose rates were compared to those calculated by the removal diffusion theory computer program MAC; a calculation in 18 removal groups and 31 diffusion groups. Agreement is excellent for fast-neutron flux and gamma-ray dose rate in the concrete shield and for thermal and epithermal flux in the graphite reflector. Calculations of thermal and epithermal fluxes in the concrete shield are in lesser agreement with measured values; generally within a factor of 2.