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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.
R. N. Nair, T. M. Krishnamoorthy
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 235-245
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35252
Articles are hosted by Taylor and Francis Online.
Mathematical models have been developed to predict the spatial and temporal profiles of radionuclide concentration in the near field and far field of a shallow land burial facility. The disposal facility considered is a reinforced concrete vault located 2.9 m above the water table. The source term is derived from leaching considerations based on diffusion-controlled kinetics for the transfer of radionuclides from the cylindrical waste form into the surrounding pore water of the backfill material. The concentration of radionuclides in the backfill at the bottom boundary of the vault is converted to a release rate into the near field using the outgoing water flux. The delay and decay during transit in the sand and soil layers are taken into account while evaluating the concentration and release at the near field-water table boundary. Using this release rate as the inlet flux, the concentration of radionuclides in the groundwater has been computed using a two-dimensional model. Results indicate that the vault facility with cement as the backfill material could contain almost all the radionuclides commonly encountered in the waste stream generated during the operation of nuclear power plants. However, the storage of some of the long-lived radionuclides produced in fuel reprocessing plants such as 79Se, 99Tc and 129I in the vault facility need to be regulated for restricting the resultant dose within the apportioned dose limit prescribed for the facility.