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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.
Smaeil M. Aceil, Doyle R. Edwards
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 123-130
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34498
Articles are hosted by Taylor and Francis Online.
A model correlating the minimum critical power ratio (MCPR) of standardized boiling water reactors (BWRs) to a set of thermal-hydraulic variables in parameter space is developed. A statistical approach with fractional factorial sampling along with response surface methodology and orthogonal central composite design are employed. The COBRA-II computer code, after modifications to include MCPR calculation, is used to simulate the thermal hydraulics of the BWR/6. The sensitivity is obtained by differentiating a quadratic equation that represents the state of the system with respect to its constituent variables. Taking this correlation as a joint multivariable probability distribution function and using crude Monte Carlo integration techniques, the probability of boiling transition during normal operation in a standardized BWR/6 is estimated. The result agrees very well with data available in open literature.
