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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
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%.