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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.
Hongbin Zhang (INL), Cole Blakley (Utah State Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 252-261
An approach to uncertainty quantification and sensitivity analysis with coupled simulations of VERACS/ FRAPCON and VERA-CS/BISON was developed within the Multi-Physics Best Estimate Plus Uncertainty (MP-BEPU) safety analysis framework LOTUS. A single assembly model was developed for the VERA-CS simulations and FRAPCON and BISON models were developed for the hot rod in the assembly. Uncertainty quantification and sensitivity analysis were performed with 23 uncertain input parameters for the coupled VERA-CS/FRAPCON simulations and with 31 uncertain input parameters for the coupled VERA-CS/BISON simulations. The maximum fuel centerline temperature (MFCT) and gap conductance at peak power (GCPP) were selected as the figures of merit (FOM). Pearson and Spearman Correlation Coefficients, Sobol Indices and Moment Independent Delta Measures were considered in the sensitivity analysis.