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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
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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?
Robert P. Wadkins, Richard G. Ambrosek, Michael W. Young
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 465-472
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32354
Articles are hosted by Taylor and Francis Online.
Critical heat flux (CHF) tests were performed at low pressure in a close-packed rod bundle. The electrically heated test bundle had geometrical configurations the same as those of the Power Burst Facility nuclear core. Existing low-pressure CHF correlations, namely, those of Bernath and Lund, did not correlate well with the test data. The Bernath correlation overpredicts CHF in some cases by a factor of 5 when compared with measured values. Lund’s correlation overpredicts CHF at measured CHF values above 1.5 MW/m2, and underpredicts CHF at measured CHF values below 1.5 MW/m2. These CHF tests provided the first close-packed rod bundle data with a sufficient data base to develop a correlation. The study examined CHF with absolute coolant system pressures of 117 to 255 kPa, mass velocities of 1992 to 4830 kg/s· m2, and subcooling of up to 53°C, with a rod spacing of 1.02 mm. The effect of rod bowing was examined with the rod spacing reduced in varying degrees to a minimum of 0.0508 mm. Motion pictures of the rod bundle during CHF with nominal spacing and bowed rods show that CHF occurs in the rod gap and does not propagate azimuthally on the rod surface. A CHF correlation developed from the test data correlates the data with a standard deviation of 8.79%.
