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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.
Sherif S. Nafee
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 328-336
Technical Note | Radiation Transport and Protection | doi.org/10.13182/NT13-106
Articles are hosted by Taylor and Francis Online.
The calibration of high-purity germanium gamma-ray cylindrical detectors using bar (parallelepiped) sources is carried out analytically using the probability correction approach. Improved expressions for the source self-attenuation coefficient have been included in the present algorithm based on the accurate calculation of all possible path lengths covered by the gamma ray inside the bulky source. Moreover, the full-energy peak attenuation coefficient μp is included in the present algorithm. The sources were positioned at long distances from the detector window so that the coincidence summing effects could be neglected. Remarkable agreement between the measured efficiency values and the corrected efficiency values calculated by the present technique was observed. The percentage relative differences for the results calculated in this way from experimental values are at least 25% smaller than those observed and reported by the direct mathematical method in previous work.
