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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.
Constantine P. Tzanos
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 5-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34113
Articles are hosted by Taylor and Francis Online.
A method was developed for the analysis of a once-through steam generator that is based on a multinode movable boundary formulation and an accurate description of the departure from nucleate boiling boundary. In the development of this method, a liquid-metal reactor steam generator was used as a reference design. To evaluate its performance, the Energy Technology Engineering Center steam generator shutdown experiment in the once-through mode was analyzed. Also, the predictions of this method were compared with those of another steam generator code. These analyses showed that the predictions of this methodology agree very well with the experimental measurements and the predictions of the other code. The maximum difference between the temperatures predicted by this model and measurements was ∼5 K.
