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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.
Mahmoud Z. Youssef
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1552-1567
Neutronic and Shielding | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A39984
Articles are hosted by Taylor and Francis Online.
Described are procedures to be followed in applying cross-section sensitivity and uncertainty analysis to arrive at estimates for the uncertainty associated with an integrated reactor performance parameter R. Means to reduce such uncertainty are outlined. The pertaining computational codes used as analytical tools to carry out the cross-section sensitivity/uncertainty analysis are reviewed with emphasis on their current limitations and possible improvements. The range of the uncertainty in the prediction of the tritium breeding ratio TBR due exclusively to current uncertainties in the nuclear data field is presented as an application for the sensitivity and uncertainty methods and codes.
