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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.
Chien Chung, Chin-Hsuen Tsai
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 346-353
Technical Paper | Radiation Protection | doi.org/10.13182/NT96-A35214
Articles are hosted by Taylor and Francis Online.
A method to monitor in situ the dose rate from the gaseous radionuclide 41 Ar is developed using a portable gamma-ray spectrometer. A high-purity germanium detector with a sensitivity of 0.358 nSv/h per count per minute is used to calibrate 1294-keV gamma rays emitted from radioactive 41 Ar. Field measurements are conducted both inside and outside of the containment of a nuclear reactor during full-power operation, and iso-dose rate contour curves are mapped. The in situ measurement can be readily performed at various locations near a nuclear reactor with a 14-kg portable spectrometric unit. The detection limit for a 1-h counting period is as low as 0.35 nSv/h for the gaseous 41 Ar. One can use the method and field measurements developed in this research to quantitatively determine the gaseous fission products of krypton and xenon dispersed from a nuclear power plant.