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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.
Robert P. Martin
Nuclear Technology | Volume 193 | Number 1 | January 2016 | Pages 96-112
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NT14-143
Articles are hosted by Taylor and Francis Online.
This paper reviews the historical and contemporary precedence regarding the development of knowledge, its reformulation in computer codes, and subsequent application in decision making. It highlights the practical challenges of this process as it applies to the investigation of engineered systems to deliver on both promised benefits and protection from postulated failures. A model for demonstrating model content, completeness, and consistency is described, invoking and extending a knowledge/content model attributed to Popper. While the specific example examining the evolution of the thermal-hydraulic knowledge base applied for nuclear power plant safety analysis and its capture in the RELAP series of computer analysis codes is presented, the framework is general, true to the scientific method, and thus broadly applicable. It concludes that while content of our knowledge base is perpetually increasing, completeness and consistency are fundamentally unattainable; however, within a well-designed evaluation methodology, measurable proof, sufficient for regulatory deliberation, is possible.