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April 3–5, 2025
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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.
Kazuichiro Hashimoto, Kunihisa Soda, Hideo Sekiya
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1058-1066
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27697
Articles are hosted by Taylor and Francis Online.
A thermal-hydraulic analysis of the initial 174 min of the Three Mile Island Unit 2 (TMI-2) accident was performed using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage)-PM1/TMI code. The purpose of the analysis was to verify whether the THALESPMl/TMI code is capable of describing an accident progression in an actual plant. The initial and boundary conditions were based on the TMI-2 Standard Problem data base that was used by the Organization for Economic Cooperation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations in performing the TMI-2 Analysis Exercise. The analytical results generally agree with the actual behavior, indicating that the physical models employed in the code are reasonable. Better results were obtained using this analysis concerning the core degradation behavior in the early phase of the transient in which the debris node was assumed to remain at the original location. However, the physical models for the fuel relocation and debris formation need further improvement to be consistent with accident progression in the later phases of the transient.