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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.
David W. Esh, Barry E. Scheetz
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 241-251
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3271
Articles are hosted by Taylor and Francis Online.
The chemical and mineralogical conditions of the near-field, i.e., that area in the vicinity of the waste materials, may be significantly altered from ambient conditions by thermohydrological processes resulting from the placement of heat-generating radioactive materials in a geologic repository. Models are developed linking the thermohydrological effects simulated with TOUGH2 to a nonreactive aqueous species (chloride). Perturbations in near-field chemistry from the ambient conditions may have potential impacts on engineered barrier system (EBS) performance, waste-form degradation processes, and radionuclide transport. The results of thermohydrological simulations with TOUGH2 utilizing various conceptual models for fracture representation are coupled to simple chemical models (density and osmotic effects are neglected) to demonstrate the complexity and potential magnitude of thermohydrochemical (T-H-C) processes. The concentration of chloride in solution returning to the EBS following dryout, in extreme cases, is predicted to exceed 100 000 mg/l. The dimensionality of the problem and the rate at which the tuffaceous rocks rewet significantly affect the magnitude of the thermohydrological impact on chloride redistribution. A process metric (initial rewetting rate and distribution) that is ignored when evaluating thermohydrological response is very important when a more complex coupling (T-H-C) is considered.