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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.
Hee Taek Chae, Jong Hark Park, Heonil Kim, Soon Heung Chang
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 287-293
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3567
Articles are hosted by Taylor and Francis Online.
Critical heat flux (CHF) tests using rod bundles were performed under low-flow conditions to supplement the CHF database for HANARO fuel. The test rod had the same geometric configuration as the HANARO fuel, and its aluminum cladding with fins was made by coextrusion on the stainless steel heating tube. Three types of test sections were used: hexagonal with seven rods, triangular with three rods, and rectangular with four rods. Each test bundle has three spacers axially, and a view window is located in the upper region of the test section. Flow patterns until the CHF condition are typically varied from bubbly flow to annular flow, and then CHF occurs through the long annular flow period. A total of 36 bundle CHF data were obtained from the 3 test sections. The results showed that the CHFs for bundles are larger than those for a single rod with the same geometrical dimension by a maximum 26% as the mass flux changes. It is considered that these results are induced by the enhancement of the turbulence and thermal mixing generated by the spacers. In addition, measurement of the onset of nucleate boiling (ONB) in the rectangular bundle was attempted using sound signals. A hydrophone was attached near the outlet wall of the test section. Hydrophone signals around the ONB point were measured and analyzed based on the frequency through the real fast Fourier transform. Frequency analysis showed clear differences in the power spectral densities for two different frequency ranges before and after ONB, which verifies the usefulness of sound signals for ONB detection.