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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.
Eric T. Beaumont, Randall H. Jacobs
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 146-157
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2858
Articles are hosted by Taylor and Francis Online.
An analysis consisting of several transients was performed to benchmark the RETRAN02 Mod5 model for LaSalle units 1 and 2 to startup test measurements. Benchmarks to startup tests are an important step in validating a RETRAN model. The five transients chosen were as follows: a two-recirculation-pump trip, a pressure regulator setpoint change, a feedwater level setpoint change, a full main-steam-line-isolation event, and a generator load rejection with bypass. These transients were chosen to examine different aspects of the RETRAN model to provide a complete test of each system.Each of the five transients had a different set of initial conditions (e.g., power, flow). The RETRAN model was initialized at the startup test conditions, and the FIBWR2 code was used to determine the RETRAN inputs for the core pressure and bypass flow distributions. All of the RETRAN analyses used the RETRAN one-dimensional kinetics option, and the one-dimensional kinetics cross sections were developed based on Commonwealth Edison Company methodology. The LaSalle base model, transient specific changedeck, and transient specific cross-section file were used to initialize and facilitate each transient in RETRAN.The RETRAN predictions for each transient were compared with the measured plant data. These comparisons were evaluated using a predetermined acceptance criterion. The parameters of interest for each of the startup tests were shown to be within the acceptance criterion. Therefore, the benchmark results provide a high confidence that the RETRAN model is a valid and accurate representation of the LaSalle County nuclear stations for a broad spectrum of transient analysis.