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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.
Chi H. Kang, Dale B. Lancaster
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 292-304
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2948
Articles are hosted by Taylor and Francis Online.
A flat, uniform axial burnup assumption, preferred for its computational simplicity, does not always conservatively estimate the pressurized water reactor spent-fuel-cask multiplication factors. Rather, the reactivity effect of the significantly underburned fuel ends, usually referred to as the "end effect," can be properly treated by explicit modeling of the axial burnup distribution based on limiting axial burnup profiles. An alternative approach to this laborious explicit modeling is to augment the multiplication factor determined from an axially uniform calculation by an appropriate keff bias. Based on the observation that the end effect increases with a decrease in the cask size, conservative keff bias curves are determined by applying the limiting axial burnup profiles and assuming a single-assembly cask configuration. However, because of their conservative nature, the keff bias curves are not recommended unless there is a large reactivity margin in the particular cask of interest.The horizontal burnup distribution poses less reactivity concern simply because the limiting arrangement in a cask is an unlikely event. The possibility of two or more assemblies with low burnup zones placed inward and next to each other is small, while the underburned fuel ends will surely be next to each other. Regardless, the reactivity effect of the horizontal burnup distribution is bounded by assuming a conservative horizontal burnup gradient within individual assemblies and the most reactive arrangement of multiple assemblies in spent nuclear fuel casks. This approach can have a significant effect on small cask designs where the orientation of fuel assemblies has a substantial influence on the calculated multiplication factor because of the large radial neutron leakage.