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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, K. Kosako, H. Maekawa, T. Nakamura, M. A. Abdou, E. F. Bennett, A. Kumar, Y. Watanabe, M. Z. Youssef
Fusion Science and Technology | Volume 28 | Number 2 | September 1995 | Pages 305-319
Technical Paper | Fusion Neutronics Integral Experiments — Part II / Blanket Engineering | doi.org/10.13182/FST95-A30648
Articles are hosted by Taylor and Francis Online.
A pseudoline source is realized by using an accelerator-based deuterium-tritium point-neutron source. The pseudoline source is obtained by time averaging of the continuously moving point source or by superposition of the finely distributed point sources. The line source is utilized for fusion blanket neutronics experiments with an annular geometry to simulate a part of a tokamak reactor. The source neutron characteristics are measured for two operational modes for the line source: the continuous and the stepwise modes, with activation foil and NE-213 detectors, respectively. The neutron source characteristic is calculated by a Monte Carlo code to give a source condition for a successive calculational analysis of the annular blanket experiment. The reliability of the Monte Carlo calculation is confirmed by comparison with the measured source characteristics.
