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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.
Dong Won Lee, Suk Kwon Kim, Young-Dug Bae, Yang Il Jung, Jeong Yong Park, Yong Hwan Jeong, Byung Yoon Kim
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 165-169
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12346
Articles are hosted by Taylor and Francis Online.
For the second qualification of the blanket First Wall (FW) procurement of the International Thermonuclear Experimental Reactor (ITER), a semi-prototype of the FW has been designed with increased local surface heat flux up to 5 MW/m2. In order to investigate the fabrication procedure and methods, two types of mock-up were fabricated; one was with twelve Be tiles for high heat flux test to check the joining integrity between Be tiles and the bending Cu block and the other was for testing the thermal-hydraulic prediction by commercial code, ANSYS-CFX when it has a complex geometry such as hypervapotron, which was used for designing the semi-prototype. The former was successfully fabricated and the test conditions were obtained through the preliminary analysis with ANSYS-CFX. The later was successfully fabricated and the test with KoHLT-2 (Korea Heat Load Test facility) was performed; mass flow rate of inlet coolant was the same as the ITER condition and heat flux was loaded up to 0.65 MW/m2. The results show that the temperature of the mock-up can be predicted using the ANSYS-CFX even with the complex geometry.