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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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Latest News
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.
Yassin A. Hassan
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 257-267
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33609
Articles are hosted by Taylor and Francis Online.
Three-dimensional fluid and thermal mixing analysis of a full-scale cold leg and downcomer of a Babcock & Wilcox-designed pressurized water reactor is performed. The impetus of the present study is to provide an accurate estimation of the local fluid temperatures in the cold leg and downcomer when the cold high-pressure safety fluid is injected into the cold leg carrying a hot fluid. Such temperature predictions are needed in resolving the so-called pressurized thermal shock issue in the nuclear industry. The unique feature of this study is the use of the accurate mass-flow-weighted skew-upwind scheme to approximate the convective transport terms in the COMMIX-1A code approximation of the fluid energy equation. This new scheme is shown to considerably reduce the false diffusion that plagued multidimensional thermal-hydraulic applications. The computed fluid velocity patterns and temperature predictions have shown similar behavior to the flow visualization and temperature field measurements in scaled experiments.