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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.
M.Z. Youssef, Y. Watanabe, M. Abdou, M. Nakagawa, T. Mori, K. Kosako, T. Nakamura
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1299-1308
Blanket Nucleonics Experiment | doi.org/10.13182/FST89-A39869
Articles are hosted by Taylor and Francis Online.
Several fusion-oriented integral experiments were performed in Phase II of the U.S./JAERI Collaborative Program on Fusion Neutronics where the geometrical configurations and source condition closely simulate the incident spectrum in fusion reactors. The main objective of the program is to estimate the uncertainties involved in predicting tritium breeding rate in Li2O and other neutronics parameters in fusion blankets that include engineering features (i.e., first wall, multiplier). In Phase II, the Li2O test assembly is placed on one end of a Li2CO3 enclosure that houses the D-T neutron source. Predicted local and integrated tritium production rates (TPR) from 6Li(T6), 7Li(T7) and natural lithium (TN) were compared to measurements in various configurations that included reference, first wall and beryllium multiplier experiments (Phase IIA) in addition to repeating these experiments with a FW/Be layer covering the interior surface of the Li2CO3 enclosure (Phase IIB). Other neutronics parameters that included source characterization by foil measurements, in-system reaction rates, and in-system spectrum measurements were also analyzed. The analyses were carried out independently by both parties using various 3-D Monte Carlo codes and 2-D discrete ordinates codes and data libraries. The results of the analyses are reported in this paper with emphasis placed on the impact of the beryllium data on the discrepancies found between predictions and measurements.