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Young Members Group
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
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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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.
Michael P. Manahan
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 324-333
Technical Paper | Material | doi.org/10.13182/NT89-A34254
Articles are hosted by Taylor and Francis Online.
Small flakes that consist primarily of magnetite have been discovered on the secondary side of the steam generator of the Three Mile Island Unit 1 plant. These iron oxide flakes are believed to cause significant increases in flow resistance, which in turn causes abnormal increases in steam generator water level. It is necessary to measure the physical properties of the tube scale so that the maximum amount of loose flakes can be generated prior to hydrodynamic cleaning (water slap). It is also important to study the flake properties to shed light on the flake formation and transport mechanisms. Once the physical properties of the tube scale are determined, the effects of hydrodynamic cleaning (water slap) can be optimized by preconditioning the scale. There are several preconditioning options including prewetting, predrying, and thermal cycling of the steam generator tubes. Understanding the physical properties of the scale would also be beneficial in optimizing the water slap technique itself. Elastic modulus, fracture stress, thermal expansion, and swelling of the flakes were measured. With one exception, all of the flakes studied were either one-or two-layered as judged by microstructural variation. The fracture stress of the flake materials tested was in the range of 20.0 to 113.8 MPa (2.9 to 16.5 ksi). There did not appear to be a substantial change in the range of stresses measured at elevated temperatures. There was no evidence of delamination during bend testing. The mean coefficient of linear thermal expansion was a factor of ∼2 larger than that of Fe3O4. The maximum amount of swelling measured was 0.0012%, which is consistent with earlier data on flakes from the Oconee-2 plant.