ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Jul 2024
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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.
A. L. Pitner
Nuclear Technology | Volume 30 | Number 1 | July 1976 | Pages 77-85
Technical Paper | Material | doi.org/10.13182/NT76-A31626
Articles are hosted by Taylor and Francis Online.
Eighteen boron carbide specimens were irradiated for 355 effective full-power days in the Experimental Breeder Reactor II to maximum burnups of 82 x 1020 capture /cm3. Baseline specimens were patterned after Fast Flux Test Facility reference boron carbide, and material variables of 10B enrichment, pellet density, grain size, and stoichiometry were investigated in the test. Irradiation temperatures ranged from 1175 to 1570°F (635 to 855°C). Each specimen was individually instrumented to measure temperature and helium release continuously during irradiation.Postirradiation examination provided information on pellet integrity, swelling, tritium retention, and compatibility with stainless-steel containment components.
