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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.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
J. E. Hench, D. J. Liffengren
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 544-550
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30851
Articles are hosted by Taylor and Francis Online.
The experimental results of fuel rod failure on the heat transfer effectiveness of spray cooling a Zircaloy-clad simulated BWR fuel bundle were evaluated from the design engineer viewpoint to determine the adequacy of the emergency core cooling system (ECCS) design. The overall results of the full-size 49-rod Zircaloy-clad internally pressurized bundle indicate that the ballooning and perforation associated with cladding failure did not significantly change the heat transfer effectiveness (i.e., peak cladding temperatures) of the ECCS spray cooling mode. Furthermore, the distortion was local in nature so the flow area reduction would not affect the ability of the ECCS flooding mode to accomplish the design objectives.