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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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February 2025
Nuclear Technology
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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?
Vincent P. Manno
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 281-288
Technical Paper | Fuel | doi.org/10.13182/NT80-A32474
Articles are hosted by Taylor and Francis Online.
The current regulatory requirement that peak cladding temperatures (PCTs) never exceed 1204°C (2200°F) at any time during a loss-of-coolant accident (LOCA) is frequently the most limiting factor in setting core peaking factor limits. Of the many plant specific characteristics involved in predicting a fuel rod’s thermal response to a LOCA, the containment or “back” pressure plays a significant role, especially in pressure suppression pressurized water reactor (PWR) containments. The back pressure effect is studied by comparing the predicted PCT histories at back pressure levels of 138, 155, 172, and 207 kN/m2 (20, 22.5, 25.0, and 30 psia). A typical four-loop PWR with 15 × 15 fuel assemblies is analyzed. The analysis is performed using an in-house LOCA code named HEATUP-R/AEP, which calculates fuel thermal response during core reflood. In addition to temperature, the reflood rates, exit qualities, and cladding oxidation rates are studied. Results show significant increases in PCTs at lower pressure due to enhanced steam binding in the coolant loops.