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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.
R. Maingi, J. Gilligan, O. Hankins, L. Owen, P. Mioduszewski, T. Uckan
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1778-1782
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29600
Articles are hosted by Taylor and Francis Online.
A critical issue in long-pulse tokamak discharges is the need for density control and power-handling capability in the presence of wall outgassing, neutral beam injection, and pellet fueling. Direct particle and energy exhaust in Tore Supra is obtained with a system of pump limiters, including six located at the bottom of the machine and a large horizontal module at the outer midplane. This paper focuses on two-dimensional (2-D) modelling of the scrape-off-layer (SOL) and outboard pump limiter, using the MHD fluid code b2 and the neutral transport code DEGAS. Temperature, density, and ion flux data from Langmuir probes in the throat of the limiter are used along with estimates of the power scrape-off-length from infrared camera data to obtain a self-consistent description of the SOL plasma/neutral source distribution within the limiter and throughout the SOL. Good agreement with measured quantities is obtained, and three to four iterations of the b2/DEGAS calculation are necessary for convergence.
