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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
G. Ramponi, D. Farina, M. A. Henderson, E. Poli, G. Saibene, H. Zohm
Fusion Science and Technology | Volume 52 | Number 2 | August 2007 | Pages 193-201
Technical Paper | Electron Cyclotron Wave Physics, Technology, and Applications - Part 1 | doi.org/10.13182/FST07-A1498
Articles are hosted by Taylor and Francis Online.
The ability of ITER electron cyclotron (EC) wave launchers to drive localized current at various plasma locations is analyzed by means of beam-tracing codes, looking at extended physics application of EC current drive in ITER and at possible synergy between the two launchers. Calculations for an improved design of the upper launcher, based on four upper ports and front steering mirrors allowing both optimum focusing of the beams and an extended plasma deposition region, show that narrow, high peak current density profiles may be maintained over the radial range 0.4 p 0.9. Calculations for the equatorial launcher, where the control of the deposition location is achieved by varying the toroidal injection angle , point out that because of poor localization and incomplete power absorption at large toroidal angles ( > 40 deg), the power deposition and current drive location by this launcher is limited to p 0.55. Moreover, it is shown that performance close to the center can be improved with a poloidal tilt of the low and top front mirrors. The main aim of this study is to provide guidance to the design of both launchers in order to optimize their performance, depending on the physics application.