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ANS Student Conference 2025
April 3–5, 2025
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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.
Akitoshi Hotta, Makoto Honma, Hisashi Ninokata, Yusuke Matsui
Nuclear Technology | Volume 135 | Number 1 | July 2001 | Pages 1-16
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3202
Articles are hosted by Taylor and Francis Online.
In this study, applicability of the TRAC/BF1-ENTRÉE code to regional instability was demonstrated in two parts. In Part I, fidelity of numerical models was studied with regard to the density-wave oscillation. Based on the FRIGG-4 loop test, predictability of the code has been demonstrated. An appropriate time integration scheme was explored, and it was found that the numerical viscosity can be minimized by applying the semi-implicit method and specifying the material Courant number close to unity. Applicability of the code was studied for simulating parallel channel configurations. The bypass channel effect was quantified as a function of its flow area and power level. The influence of flow mixing at the upper and lower plena was studied.
