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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.
Yury A. Bezrukov, Sergey A. Logvinov, Vladimir N. Ul'yanovsky, Nikolay A. Strebnev
Nuclear Technology | Volume 146 | Number 2 | May 2004 | Pages 122-130
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3492
Articles are hosted by Taylor and Francis Online.
In this paper, results of experimental studies of the coolant flow mixing at different boron concentration and different temperature in the VVER-1000 reactor downcomer and lower plenum are presented. Studies concerning boron dilution were carried out on the reactor model in scale 1:5 for cases of reactor coolant pump (RCP) startup and resumption of natural circulation during a small-break loss-of-coolant accident. It has been shown that for RCP startup, the effect of Reynolds number on mixing is negligible. Studies of flow mixing in the reactor downcomer were carried out applied to emergency core cooling system water injection into the cold loop leg and reactor downcomer. Results of the tests on model and reactor have been analyzed, and recommendations for calculations have been provided.