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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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!
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Seconds Matter: Rethinking Nuclear Facility Security for the Modern Threat Landscape
In today’s rapidly evolving threat environment, nuclear facilities must prioritize speed and precision in their security responses—because in critical moments, every second counts. An early warning system serves as a vital layer of defense, enabling real-time detection of potential intrusions or anomalies before they escalate into full-blown incidents. By providing immediate alerts and actionable intelligence, these systems empower security personnel to respond decisively, minimizing risk to infrastructure, personnel, and the public. The ability to anticipate and intercept threats at the earliest possible stage not only enhances operational resilience but also reinforces public trust in the safety of nuclear operations. Investing in such proactive technologies is no longer optional—it’s essential for modern nuclear security.
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%.