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The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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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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.
Stephanie H. Bruffey, Robert T. Jubin
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 159-169
Technical Paper | doi.org/10.1080/00295450.2017.1369802
Articles are hosted by Taylor and Francis Online.
In 2010, the Idaho National Laboratory was in the process of removing legacy materials from one of their hot cells. As part of this clean-out effort, five metal capsules and some loose zeolite material were identified as test specimens produced in the late 1970s as part of research and development (R&D) conducted under the Airborne Waste Management Program. This specific R&D effort examined the encapsulation of 85Kr within a collapsed zeolite structure for use as a potential waste form for long-term storage. These reclaimed capsules and loose material presented a unique opportunity to study a potential 85Kr waste form after three half-lives have elapsed. Of the five capsules, the walls of two had been cut or breached during previous experiments. The aim of this study was to produce mounted samples from the two breached samples that could be handled with minimal shielding, assess the physical condition and chemical composition of the capsule walls for each breached sample, and determine if any loss of capsule wall integrity was directly attributable to rubidium, the decay product of 85Kr. The sectioning and mounting of the breached capsules was successfully completed. The capsule wall of these 85Kr legacy waste form capsules was examined by optical microscopy and by scanning electron microscopy and energy-dispersive spectroscopy. Substantial corrosion was observed throughout each capsule wall. The bulk of the capsule wall was identified as carbon steel, while the weld material used in capsule manufacture and/or sealing was identified as stainless steel. A notable observation was that the material used for Kr encapsulation was found adhered to the walls of each capsule and had a chemical composition consistent with zeolite minerals. The results of studies on the retention of Kr by the encapsulation material will be discussed in a subsequent paper. Three legacy capsules remain in storage at Oak Ridge National Laboratory and may not have been breached. These represent an exciting opportunity for continued 85Kr waste form studies and will provide more indication as to whether the corrosion observed in Capsules 2 and 5 is attributable to the breach of the capsule, to Rb-induced corrosion, or to another cause.