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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
Jan 2024
Latest Journal Issues
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. A. Basmajian, A. L. Pitner, D. E. Mahagin, H. C. F. Ripfel, D. E. Baker
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 238-248
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31190
Articles are hosted by Taylor and Francis Online.
Fast neutron spectra irradiations of boron carbide are being performed. Hardened spectra irradiations in ETR, material irradiations in EBR-II, and EBR-II components yielded the data which are being used for design and analysis of FFTF control elements. Boron carbide was irradiated at temperatures from 800 to 1600°F at burnup values from 2 × 1020 to 20 × 1020 captures/cm3. A variety of material parameters such as pellet density and boron-to-carbon ratios were measured. Data on gas release, swelling, thermal conductivity, microscopy, and compatibility were found to differ substantially from data obtained in thermal reactors.
