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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.
Juan J. Casal, Jan Krouthén, Manuel Albendea
Nuclear Technology | Volume 151 | Number 1 | July 2005 | Pages 51-59
Technical Paper | Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks | doi.org/10.13182/NT05-A3630
Articles are hosted by Taylor and Francis Online.
The introduction of the SVEA-96 Optima generation of advanced boiling water reactor fuel designs implies a further increment in complexity and heterogeneity that needs to be supported by accurate calculation tools. In order to take advantage of the improved economics offered by these modern fuel designs while simultaneously assuring safe and reliable reactor operation, both the reload design process and the online core monitoring procedures must be based on appropriate calculation methods. The modeling of transition cores involving the gradual introduction of these new fuel designs poses a severe challenge for the current core physics methods. Recognizing this, Westinghouse has engaged in a continuing process of improving its core physics calculation packages. This development program is supported by a comprehensive validation effort to demonstrate the accuracy and reliability of the improved methods as well as to identify areas requiring further development. The purpose of this paper is to summarize some of the results of this program.