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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.
Y. Higashizono et al.
Fusion Science and Technology | Volume 47 | Number 1 | January 2005 | Pages 297-299
Technical Paper | Open Magnetic Systems for Plasma Confinement | doi.org/10.13182/FST05-A669
Articles are hosted by Taylor and Francis Online.
The neutral transport was studied in the anchor cell. The H line intensities were measured by using axially aligned H detectors. It was found that the intensity is considerably dependent on ECRH and GP#3,4. A 5ch H detector was newly installed in the outer-transition region of the anchor-cell. From the measurement of the spatial distributions, the vertical intensity profile is estimated to be about 2.5 cm on the half width half maximum, while the horizontal distribution shows roughly flat around Z=-670 cm. The above characteristics were discussed with aid of neutral transport simulation using DEGAS Monte-Carlo Code.
