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
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. O. Cermak, R. H. Leyse, D. P. Dominicis
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 557-562
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30853
Articles are hosted by Taylor and Francis Online.
The effects of flow blockage on bottom-cooling heat transfer effectiveness were studied in the PWR-FLECHT program. Blockages of 50 and 75% of the flow area of a 5 × 5 array in the center of a 7 × 7 rod bundle were studied with 12-ft-long heater rods with an axial cosine heat generation distribution of 1.66 peak-to-average and decay-heat simulation. The test section consists of 42 heated rods (fuel rods) and 7 non-heated tubes (control rod thimbles). Flow blockage is effected by a -in.-thick flat plate mounted at the peak heat generation location (6-ft elevation) with the heater rod thermocouples being located ∼1 in. downstream from the flow blockage plate. The results of a flooding rate of 6 in./sec showed the maximum temperature rise in the heater rod was the same for 0, 50, and 75% flow blockage. Lower flooding rates of 4- and 2-in./sec showed higher temperature rises in the heater rod for the 0% flow blockage case than for the 75% flow blockage case. These flow blockage tests demonstrate that bottom-flooding heat transfer effectiveness is not impaired with the flow blockage configurations tested. Further tests are planned at flow area blockages of 90%.