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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.
Eric Pinton, Bernard Duret, Georges Berthoud
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 332-351
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3005
Articles are hosted by Taylor and Francis Online.
To improve the knowledge of the behavior of a UF6 container during a fire, an experimental project called Tenerife was conducted by the Commissariat à l'Energie Atomique. Three tests with UF6 with different kinds of heating and temperature furnaces were carried out. The main information obtained from monitoring temperature and pressure during the heating tests is as follows:1. The presence of a strong thermal contact resistance at the solid UF6-steel interface.2. The rupture of the solid crust at the top of the container, a crust formed during container cooling after filling, for a pressure reaching 1.5 bars (triple point). This leads to the beginning of boiling heat transfer and notably film boiling, followed by transition boiling and nucleate boiling.3. The appearance of the liquid stratification with the beginning of nucleate boiling. It can accelerate the rise in pressure because of the reduction of mass transfer by condensation to the liquid-gas interface. This stratification is preserved with the natural convection regime that replaces the nucleate boiling after the end of heating.4. After rupture of the upper UF6 crust, the pressure increase may be delayed by different wetting of the UF6 on the steel wall.Also, these tests were allowed to build and validate a scenario that has been reproduced in a numerical model.