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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.
Masabumi Nishikawa, Hiroki Takata, Toshiharu Takeishi, Kozo Kamimae
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 386-389
Technical Paper | Tritium Science and Technology - Tritium Measurement, Monitoring, and Accountancy | doi.org/10.13182/FST05-A949
Articles are hosted by Taylor and Francis Online.
Feasibility of the monitoring way of HTO in air to follow the tritium level in water contained in a small shallow beaker with open surface placed still in a room was discussed in this study. It is considered that the isotope exchange reaction between tritiated water in air and water in a beaker, the evaporation or condensation reaction of water at surface and the diffusion of tritium in water played the important roles in the tritium transfer phenomena through the air-water interface. Using the mass transfer coefficients obtained in the previous paper, change of tritium level in water contained in a shallow open beaker was numerically estimated and comparison with the experimental data showed good agreement. The estimated amount of tritium released from the facility with storage pools of spent fuels from a PWR power station using the method of this study showed good agreement with the observed value evaluated from the monitor of the power station