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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.
Ziping Liu, Yu Ji, Han Zhang, Jun Sun
Nuclear Technology | Volume 208 | Number 8 | August 2022 | Pages 1337-1351
Technical Paper | doi.org/10.1080/00295450.2022.2031498
Articles are hosted by Taylor and Francis Online.
Composite materials are essential in various energy fields owing to their improved heat transfer characteristics. Due to their inhomogeneous structure, it is difficult to obtain the heat transfer details. Effective thermal conductivity (ETC) is an important lumped thermal parameter used to analyze the heat transfer process in composite materials. Existing ETC models are derived by applying a temperature difference (TD) on two opposite boundaries of the composite material to induce heat flow. However, for some composite materials, such as nuclear fuels, the effect of the inner heat source (IHS) is typically ignored. Thus, the suitability of using ETC models based on a TD scheme for composite materials with IHS still requires further investigation. In this study, first the conserved quantities of ETC of the TD and IHS schemes were determined. For normal materials of the TD scheme, the conserved quantity of ETC can be selected as heat flow, whereas for nuclear fuels of the IHS scheme, the average temperatures are recommended as the conserved quantity. Then the general ETC models for composite plate were derived considering both the TD and IHS schemes and special cases with either TD or IHS were also analyzed. Finally, based on the results of this study, the idea of studying the ETC of tristructural-isotropic or TRISO particle-based nuclear fuels is proposed.