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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.
Sridhar Hari, Yassin A. Hassan, Jiyuan Tu
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 296-309
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3095
Articles are hosted by Taylor and Francis Online.
Simulations of two different events without scram were conducted for a hypothetical research reactor, based on the High-Flux Australian Reactor (HIFAR) moderated and cooled by heavy water circulating under atmospheric pressure. The simulations were performed with the RELAP5/MOD3.2 computer program. Although the simulations neglected reactivity feedback effects, the focus on the thermal-hydraulic aspects represents a step toward full analyses of hypothetical events in HIFAR. Two simulations focused on events associated with the failure of the primary coolant circulation pumps, and three simulations focus on the events associated with the reduced heat removal via the nonavailability of heat exchangers. The critical heat flux subroutine of the RELAP program was modified to account for the concentric annular fuel element geometry of HIFAR fuel elements.
