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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.
William D. Rhodes, Raymond V. Furstenau, Howard A. Larson
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 145-158
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3083
Articles are hosted by Taylor and Francis Online.
The generic technique of applying pseudorandom, discrete-level, periodic reactivity perturbation signals to measure the reactivity-to-power frequency response function was extended to the liquid-metal reactor, Experimental Breeder Reactor-II (EBR-II). This technique was developed in the late 1960s and applied in several reactor designs with extensive testing performed at the Molten Salt Reactor Experiment. Signals employed at EBR-II included the pseudorandom binary sequence, quadratic residue binary sequence, pseudorandom ternary sequence, and multifrequency binary sequence. For all the signals employed, the resultant reactor power perturbation was small enough to be acceptable for normal at-power operation and in-place irradiation experiments. The frequency response results are compared with the zero-power frequency response function, yielding a quantitative measure of the EBR-II reactivity feedback effects. The frequency response function results are in good agreement with rod-oscillator data and model predictions. The multifrequency binary sequence concentrated 64% of the total signal power into the four feedback frequencies associated with the predominant feedback time constants. The input signal quality, characterized by the autocorrelation function and power spectra, validated the automatic control rod drive system design and operation as an effective tool for frequency response determination over the range of frequencies where important system dynamic effects occur.