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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.
H. Kakiuchi et al. (19P24)
Fusion Science and Technology | Volume 51 | Number 2 | February 2007 | Pages 280-282
Technical Paper | Open Magnetic Systems for Plasma Confinement | doi.org/10.13182/FST07-A1375
Articles are hosted by Taylor and Francis Online.
An inner mirror throat of the plug/barrier cell is one of the noticeable locations in the tandem mirror GAMMA10, because the location is the most suitable for a measurement of the ions bounced by the plug potential, which are essential for the tandem mirror confinement. A lithium beam probe was designed as a main part of the diagnostic system to measure the radial profiles of the electron and neutral particle density at the inner mirror throat. A neutral lithium beam is injected into the plasma and the light emitted from the beam is detected. We estimated the upper limit of the plasma density measurable by the lithium beam probe and discussed validity of the reconstruction for various types of radial profiles. We adopted, at first, a Gaussian type of radial profile of the density with the radius of 2.5 cm for the estimation of the upper limit of the density. It was found that the profile reconstruction was carried out well up to the peak density of 5 × 1013 cm-3, and also well even in the non-axisymmetric radial profile. This method is quite appropriate for the measurement of the density profile at the inner mirror throat.