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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.
Kazuya Idemitsu, Ken-ichiro Kuwata, Hirotaka Furuya, Yaohiro Inagaki, Tatsumi Arima
Nuclear Technology | Volume 118 | Number 3 | June 1997 | Pages 233-241
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35364
Articles are hosted by Taylor and Francis Online.
Diffusivities of cesium in a water-saturated mortar were measured in an attempt to investigate the migration of radionuclides into the matrix of the mortar. The measured penetration profiles of the tracer were composed of two parts. There was a steep slope near the surface and a gradual slope in the mortar interior. This kind of profile has been reported by many researchers. This profile was successfully explained by considering two diffusion paths in the mortar. One diffusion path was through fissures with a width of a few microns, and the other was through the intact mortar network of submicron pores. This model was supported by autoradiography of some cross sections of a mortar specimen. The volume of submicron pores was ∼95% of the total pore volume in the mortar. The order-of-magnitude values for the apparent diffusivities for cesium were 10−2 m2/s through the fissure and 10−14 m2/s through the network of pores. The effective diffusion coefficient for cesium was estimated at ∼10−13 m2/s by using the apparent diffusivities through the fissures, the aperture of the fissures, and the fissure interval. Geometric factors in the two paths were also estimated by using the apparent diffusivity and diffusion coefficients for free ions; they were estimated at ∼0.13 for fissures and ∼0.01 for the mortar matrix. This model was applied to other researchers’ data to estimate the effective diffusion coefficient. This model and estimation method show the consistency of the data from through-diffusion and penetration experiments.