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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
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?
T. R. Bump
Nuclear Technology | Volume 9 | Number 3 | September 1970 | Pages 301-308
Fuel Element Performance Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28784
Articles are hosted by Taylor and Francis Online.
The SWELL fuel element lifetime code employs the “cumulative damage” approach to estimate when the cladding of an LMFBR mixed-oxide fuel element is likely to fail under normal and off-normal conditions. In the estimating process, properties and behavior of irradiated, as well as of unirradiated, cladding are considered. A unique feature of SWELL is its use of an empirical function, developed by calibration with experimental data, which relates the pressure-exerted-on-cladding-by-fuel-swelling to the pressure-of-fission-gas-retained-in-fuel. SWELL predicts that the lifetimes of some typical fuel elements will have to be reduced significantly if the elements are to be expected to withstand rather modest off-normal conditions near end of life. However, there are reasons why the predictions may be overly pessimistic. Early results from the newer and more-detailed LIFE fuel element behavior code indicate that the accuracy with which a fuel element's operating history is followed may be important for gaining understanding of the element's behavior. To conserve computer time, the best way to simulate actual history, as jar as cladding ΔD/D predictions are concerned, appears to be to use time-averaged power (excluding downtime) for a length of time sufficient to produce the actual burnup, which happens to be the SWELL practice.