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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.
Hideaki Asaka, Yutaka Kukita, Taisuke Yonomoto, Kanji Tasaka
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 202-214
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34606
Articles are hosted by Taylor and Francis Online.
Three 0.5% hot-leg small-break loss-of-coolant accident experiments are conducted at the ROSA-IV Large-Scale Test Facility (LSTF), a volumetrically scaled full-height model of a pressurized water reactor. Three experiments simulate breaks located at the side, bottom, and top of the horizontal hot-leg piping to investigate the effects of break orientation on system thermal-hydraulic responses. Although the overall system responses in the three experiments are qualitatively the same, the break flow rate is affected significantly by the break orientation for most of the time preceding the initiation of core uncovering: The break flow rate is largest for the bottom break and smallest for the top break. The RELAP5/MOD2 code fails to predict the differences in break flow rate observed in the experiments. However, several modifications, based on separate-effect experiments, made particularly to the break flow calculation models enable this code to simulate the experimental results well.
