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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.
Y. Oyama, C. Konno, Y. Ikeda, H. Maekawa, K. Kosako, T. Nakamura, A. Kumar, M. Youssef, M. Abdou, E. Bennett
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1879-1884
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29617
Articles are hosted by Taylor and Francis Online.
Neutronics experiments for an annular blanket system have been performed using a simulated line DT neutron source. The line source was simulated by moving point source in which the annular blanket was oscillated relatively on the axis of the DT neutron target. The measurements were performed in both ways of continuous and stepwise motions. The former was applied to heavy irradiation experiments such as the foil activation method for reaction rate and Li2O pellet technique for tritium production rate (TPR). The latter was to on-line methods such as NE213 and Li-glass scintillators for spectrum and TPR of 6Li and 7Li. Especially the latter case provides contribution of neutrons generated at each point on the line source to the reaction at the detector position. This corresponds to an importance distribution at the center axis of the annular system and can be compared to the calculated adjoint flux at the source positions.