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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.
Chi-Szu Lee, Chaung Lin
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 256-266
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3874
Articles are hosted by Taylor and Francis Online.
A method that includes a genetic algorithm (GA), principal component analysis (PCA), and an artificial neural network (ANN) is adopted in the search for the power ascension path of a boiling water reactor that used to rely solely on an operator's experiences. The power ascension path is formulated as an optimization problem with thermal limits, e.g., minimum critical power ratio, maximum linear heat generation rate, and maximum average planar linear heat generation rate, and with the stability requirement serving as a constraint. The Simulate-3 code is used to calculate the reactor core status, while the optimization problem is solved through the use of the GA. Since the search domain of the GA is relatively large, the ANN, which models the power ascension path, is developed in order to quickly select the candidate solutions for further Simulate-3 calculations, permitting the algorithm to converge effectively. Meanwhile, PCA is used to reduce the ANN input vector's dimension, which improves the ANN training efficiency and pattern recognition capability. The results show that this method efficiently obtains the proper power ascension path required for meeting all constraints at different fuel exposure levels.