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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.
Ferenc Adorján, Toshio Morita
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 264-275
Technical Paper | Reactor Control | doi.org/10.13182/NT97-A35367
Articles are hosted by Taylor and Francis Online.
Recently, continuous power reactor core surveillance, which is based on fixed in-core detector readings, has exhibited a trend of growing significance. The fixed in-core sensors can only be replaced during shutdown periods; therefore, it is important to have reliable information on the quality of each detector in advance to be able to create an appropriate detector replacement schedule. During the operating cycle, the continuous core surveillance system should rely only on reliable measurements, and only an effective detector failure diagnosis can ensure avoiding falsified information. At the same time, most published signal validation methods are not well suited for an extensive set of fixed in-core detectors. A relatively simple, though powerful and robust, method is proposed that can be applied for both signal validation and early failure detection. The basic idea of the method is that inevitably there exist such process noise components in the detector signals that are characteristically correlated within some well-determined groups of sensors. The lack of such correlation most probably occurs due to some detector failure. When a smaller, localized subgroup of the detectors shows a decreased level of correlation with the majority, that is typically caused by some abnormal event in the technological process. In such cases the results of this method can be utilized as a target identification tool for the more sophisticated noise diagnostics methods. The method has been thoroughly tested with an extensive data set, including rhodium self-powered neutron detectors and assembly outlet thermocouple signals, which was collected throughout a complete operational cycle of a VVER-440/213-type pressurized water reactor.