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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.
L.J. Perkins, G.L. Kulcinski
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1107-1112
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A23006
Articles are hosted by Taylor and Francis Online.
A self-consistent procedure has been established for economic design optimization of the lithium-lead (LiPb) blanket for the MARS tandem mirror reactor. The procedure is necessarily iterative and enables progress in blanket design to be assessed in terms of the minimization of an economic figure of merit F for the complete reactor system. Typical economic design questions regarding blanket and central cell parameters such as tritium breeding ratio, neutron energy multiplication factor, thermal cycle efficiency, blanket radial thickness, magnet radii, etc., can then be addressed in terms of their influence on overall system costs. This procedure is not necessarily specific to MARS and has general applicability to fusion reactor blanket design optimization. Application of the procedure resulted in a blanket with small (∼ 38 cm) radial thickness, highly enriched (90%) lithium, adequate tritium breeding ratio (1.14) and a neutron energy multiplication and thermal efficiency approaching those for blankets of considerably larger radial dimensions.
