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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
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%.