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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Ryan Hunt, Hongjie Zhang, Alice Ying, Michael Ulrickson
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 354-358
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12379
Articles are hosted by Taylor and Francis Online.
This research reveals the results of a thermo-mechanical stress analysis of the beryllium and CuCrZr components of the Enhanced Heat Flux (EHF) First Wall (FW). Under the EHF thermal load, differential thermal expansion at the Be/CuCrZr interface can potentially lead to failure of the beryllium tiles. We have shown that the stress profile in both beryllium and CuCrZr can be improved by reducing the dimensions of the beryllium tiles covering the FW panels.In addition, our research investigated a failure condition for the FW finger's design. Specifically, we assessed the temperature profile at the CuCrZr/water interface of the EHF FW finger in the event of a single failed tile. This was done in order to determine whether or not the critical heat flux condition occurs in the coolant channel after a single tile failure. Assuming the failure of a single tile between 11.75mm and 50mm in size, temperature profiles were generated assuming flat, rectangular water cooling channels. It was found that tile failure from the edges of the finger resulted in considerably higher temperatures than tile failures at the middle of the finger. Failure of a tile along the edge of the finger may cause catastrophic failure, as the critical heat flux condition occurred at the CuCrZr/water interface even for tiles as small as 11.75mm in size.