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Division Spotlight
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.
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?
J. A. Redfield, S. G. Margolis, J. H. Murphy, G. A. Snyder
Nuclear Technology | Volume 3 | Number 4 | April 1967 | Pages 206-212
Technical Paper and Note | doi.org/10.13182/NT67-A27757
Articles are hosted by Taylor and Francis Online.
Experimental data on the loss of coolant from a pressurized-water test loop are presented. The test loop simulated the components of a full-sized reactor plant with an electrically heated test section, a pressurizer, a heat exchanger, and a circulating coolant pump. Leaks in the coolant system were simulated by rupture disks at various locations. The test results are compared with predictions using the FLASH computer program. The calculated system-pressure transients showed good agreement with the tests. The pressure differential across the test section exhibited an oscillatory behavior, as did the predictions in one of the three tests. Measured test-section temperatures showed a considerable variation from predictions; however, these temperature predictions represent an improvement over those using previous calculation methods.