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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
K. Vinjamuri, D. E. Owen
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 119-124
Technical Paper | Fuel | doi.org/10.13182/NT80-A32416
Articles are hosted by Taylor and Francis Online.
Instrumented Fuel Assembly 429, an experimental assembly designed to study helium fill gas absorption and fission gas release in pressurized uranium dioxide (UO2) fuel rods used in light water reactors, is operating in the Halden Heavy Boiling Water Reactor in Halden, Norway. Preliminary assessment of results from fuel rod internal pressure measurements and from the postirradiation examination of selected fuel rods indicates that helium fill gas is absorbed into the UO2 during the first several months of operation. The fuel absorbs ∼5.7 × 10−3 cm3 He (STP)/g UO2 at the irradiation conditions of a 5.4-MPa helium pressure and a peak steady-state fuel temperature of 1500 K. The estimated effective helium diffusion coefficient is ∼1 × 10−8 cm2/s. Periodic transients with power increases of up to 50% do not drive the helium from the UO2 matrix.