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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.
Terry Kammash
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 227-230
Fusion-Fission Hybrids and Transmutation | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13424
Articles are hosted by Taylor and Francis Online.
A fusion-fission hybrid reactor whose fusion component is the gasdynamic mirror (GDM) is proposed for power production that could meet the world's energy needs of the next several decades. The choice of the GDM is based on the fact that it is linear, axisymmetric and can operate in steady state. Since the primary role of the fusion component is to supply neutrons to the blanket, it can operate at or near “breakeven” condition, a much less stringent condition than that required for a pure fusion reactor. A large aspect ratio GDM is desirable because of MHD stability considerations, and if we choose such a geometry then a cylindrically symmetric plasma with a surrounding blanket can be treated as semi-infinite cylinders, allowing for the reactor performance to be determined by two, one-dimensional equations: one describing the time evolution of the fissile material density bred in the fertile blanket, and another describing the diffusion of fast neutrons in that region. Our choice for the blanket material is thorium-232 in order to take advantage of the thorium fuel cycle that leads to the breeding of uranium-233. Such a fuel cycle is known to be resistant to proliferation and clandestine operations. We choose to operate the GDM at 0.10 of breakeven, using deuterium-tritium (DT) plasma at a density of 1016 cm-3, and a temperature of 10keV. We find that for a reasonable design, such a reactor can generate tens of megawatts of thermal power per cm “safely” because it is “subcritical”, and “securely” because of our choice of the fuel cycle. A systems analysis reveals that about 2% of the net electric power is needed to sustain the fusion component. Moreover, we find that it takes approximately 4 months to reach steady state due to the several steps involved in the breeding cycle.