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
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Steven T. Polkinghorne
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 395-412
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35022
Articles are hosted by Taylor and Francis Online.
The ability of the ATR-SINDA fuel plate model to predict the thermal behavior of Advanced Test Reactor (ATR) fuel plates under steady-state and transient conditions is demonstrated. Computer-generated results from ten steady-state calculations and two transient calculations are compared with experimental data obtained during ATR startup tests. The calculations simulate natural convection, forced convection, flow reversal, and flow instability in specially instrumented fuel elements. Calculated temperatures are generally within 10 K of measured temperatures, confirming that ATR-SINDA is suitable for analyzing plate-type fuel.
