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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Fusion Science and Technology
February 2025
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.
M. Osakabe, M. Isobe, S. Murakami, S. Kobayashi, K. Saito, R. Kumazawa, T. Mutoh, T. Ozaki, M. Nishiura, E. Veshchev, T. Seki, Y. Takeiri, O. Kaneko, K. Nagaoka, T. Tokuzawa, K. Ogawa, K. Toi, S. Yamamoto, M. Sasao, T. Watanabe, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 131-140
Chapter 3. Confinement and Transport | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10800
Articles are hosted by Taylor and Francis Online.
On the Large Helical Device (LHD), improved confinement of fast ions by moving the magnetic axis location inward is theoretically predicted. This improvement is observed significantly in the fast-ion tail formation during the experiments of ion cyclotron range of frequency heating. The fast-ion loss effect on the tail formation is 10 times more significant in the standard configuration than in the inwardly shifted configurations. The superiority is also confirmed by the comparison of steady-state fast-ion spectra for the neutral beam (NB)-heated plasmas and by the flux decay of fast neutrals after the short-pulse injection of radial NB.
