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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.
Renzo Carta, Stella Dernini, Anna Maria Polcaro, Pier Francesco Ricci, Giuseppe Tola, Giancarlo Pierini
Fusion Science and Technology | Volume 15 | Number 1 | January 1989 | Pages 55-63
Technical Paper | Tritium System | doi.org/10.13182/FST89-A25324
Articles are hosted by Taylor and Francis Online.
Recent studies have given lower and lower values for the solubility of hydrogen isotopes in the eutectic 83Pb-17Li alloy, a candidate breeding material for the blanket of fusion machines. Therefore, thermodynamic stability for the gaseous phase under the high pressure reached at the bottom of the alloy containers can be achieved even for very low tritium concentrations in the liquid phase. A mathematical model to determine when tritium bubble nucleation occurs at an appreciable rate is presented. Considering the design parameters and the operating conditions of the Next European Torus project, it is foreseeable that the tritium generated in the blanket could evolve almost completely in the gaseous phase by forming bubbles at the top of the containers even if acceptable values of the tritium inventory (<100 g) and permeation (∼0,5 g·day−1) are maintained. This situation can be achieved if the molten alloy wets the metallic surface poorly and if the fouling on the exchanger side in contact with the cooling water causes a moderate increase of the resistance to tritium diffusion through the walls. Due to a lack of experimental data, a few assumptions are adopted, but the usefulness of the results obtained is not affected.