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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Take steps on SNF and HLW disposal
Matt Bowen
With a new administration and Congress, it is time once again to ponder what will happen—if anything—on U.S. spent nuclear fuel and high-level waste management policy over the next few years. One element of the forthcoming discussion seems clear: The executive and legislative branches are eager to talk about recycling commercial SNF. Whatever the merits of doing so, it does not obviate the need for one or more facilities for disposal of remaining long-lived radionuclides. For that reason, making progress on U.S. disposal capabilities remains urgent, lest the associated radionuclide inventories simply be left for future generations to deal with.
In March, Rick Perry, who was secretary of energy during President Trump’s first administration, observed that during his tenure at the Department of Energy it became clear to him that any plan to move SNF “required some practical consent of the receiving state and local community.”1
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.