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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.
Yuh-Ming Ferng, Yin-Pang Ma, Jer-Cherng Kang
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 186-196
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3237
Articles are hosted by Taylor and Francis Online.
Multidimensional thermal-hydraulic characteristics in the secondary side of a steam generator (SG) are simulated by way of flow-boiling models. These models essentially belong to the so-called first-principle models that are derived from the conservation laws. The calculated results can provide the whole picture of thermal-hydraulic phenomena and the localized distributions of velocity, pressure, enthalpy, and void fraction, etc. in the secondary side of the SG. In addition, with the help of these localized flow characteristics, the forcing sources can be estimated for predicting flow-induced vibration (FIV) damage suspected in the tube bundles around the U-bend region. These calculated results can provide important information to help the FIV prediction for SG U-tubes and to find where the most possible FIV damage is located.
