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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.
Toshiaki Matsuo, Takuma Yoshida
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 354-366
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3251
Articles are hosted by Taylor and Francis Online.
This study, which develops a safety assessment code for radioactive waste disposal, consists of two-dimensional analyses of underground water infiltrated flow and near-field radionuclide migration, one-dimensional analyses of far-field migration, and the dose equivalent. The study takes into account the influence of a finite absorption amount of radionuclides in an engineered barrier system (EBS).The safety assessment code is applied to 14C migration calculations. The near-field cylindrical model consists of an equally mixed region of wasteforms and backfill, bentonite, and rock. Carbon-14 coexists with 3.1 × 106 times as much 12C in the wasteforms. The distribution coefficient, maximum absorption amount, and solubility of CO32- against the equally mixed region are assumed to be 2.0 m3/kg, 3.06 mol/kg, and 544 mol/m3, respectively. Then, the release rate from the wasteforms (10-4 to 10-6/yr) and underground water detachment period from the wasteforms are examined to lower the dose equivalent by the intake of well water.The 14C concentration on the EBS boundary is 20 times as large in the case of EBS finite absorption as in the case of infinite absorption. So, the EBS finite absorption leads to absorption saturation and accelerated release of the radionuclides. The influence of the absorption saturation could not be prevented by lowering the release rate. A 3 × 104/yr detachment lowered the dose equivalent to 1/40 of the original case.