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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
L. C. Walters, J. H. Kittel
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 273-280
Technical Paper | Fuel | doi.org/10.13182/NT80-A32473
Articles are hosted by Taylor and Francis Online.
The reduction in projected sodium outlet temperatures for commercial liquid-metal fast breeder reactors has renewed the interest in metal fuels. The U-Pu-Zr or Th-Pu-U-Zr metal fuel pins, sodium bonded to stainless-steel claddings, will yield high burnup along with adequate fuel-cladding compatibility. High burnup capability is assured by designing the fuel element so that interconnected porosity and flssion-gas release occur prior to fuel-cladding contact. Interconnected porosity and fission-gas release take place at about 30% fuel-volume swelling, independent of the metal fuel composition. The U-Fs/Type 316 stainless-steel-clad driver-fuel element used in the Argonne National Laboratory Experimental Breeder Reactor II is designed to take advantage of the phenomenon of interconnected porosity, and burnups in excess of 10 at.% are typically achieved prior to cladding breach. The adequate fuel-cladding compatibility, high burnup potential, superior breeding performance, and demonstrated remote refabrication have made metal fuels an attractive alternative for fast reactor design.