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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.
Steven E. Aumeier, John C. Lee, Derek M. Cribley, William R. Martin
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 299-319
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35014
Articles are hosted by Taylor and Francis Online.
We present a new time-based cross-section parameterization scheme that allows for a more accurate global depletion analysis than current methodologies without requiring major modifications to existing codes. The new cross-section parameterization scheme makes use of few-group macroscopic cross sections calculated as a function of time at several different power levels. These cross sections are block ordered by time rather than exposure to allow for the explicit representation of instantaneous control, i.e., soluble boron concentration, and thus accurate isotopic history, within the base cross-section library. The scheme is applied to a global depletion analysis of the Slightly Enriched Spectral-Shift Reactor, an advanced converter reactor based on a pressurized water reactor design, using the CPM-2 assembly-level collision probability code and the UM2DB two-dimensional diffusion code. The depletion calculation establishes the feasibility and potential advantages of the proposed cross-section parameterization methodology and shows that through a judicious choice of spectral shift control rod withdrawal strategies, it is possible to substantially increase fuel resource utilization via the spectral shift effect while maintaining acceptable power peaking factors.
