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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.
Dale L. Smith, Charles C. Baker, Dai Kai Sze, Grover D. Morgan, M. A. Abdou, Steven J. Piet, K. R. Schultz, Ralph W. Moir, James D. Gordon
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 10-44
Overview | Blanket Comparison and Selection Study | doi.org/10.13182/FST85-4
Articles are hosted by Taylor and Francis Online.
The Blanket Comparison and Selection Study (BCSS) was a 2-yr, multilaboratory project initiated by the U.S. Department of Energy/Office of Fusion Energy. Its primary objectives were to (a) define a limited number of blanket concepts that should provide the focus of the blanket research and development (R&D) program, and (b) identify and prioritize critical issues for the leading blanket concepts. The BCSS focused on the mainline approach for fusion reactor development, namely, the D-T-Li fuel cycle, tokamaks and tandem mirror reactors (TMRs) for electrical energy production, and a reactor parameter space that is generally considered achievable with modest extrapolations from the current data base. The STARFIRE and Mirror Advanced Reactor Study reactor and plant designs, with a nominal first-wall neutron load of 5 MW/m2, were used as reference designs for the study. The study focused on