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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.
Joonhong Ahn, Myeongguk Cheon, Ehud Greenspan
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 408-430
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3851
Articles are hosted by Taylor and Francis Online.
We have developed a computation tool, WAste COMposition (WACOM) for performing a scoping study of the effects of the accelerator-driven transmutation of waste (ATW) system with a lead-bismuth-eutectic-cooled transmuter on actinide inventory and radiotoxicity reduction. WACOM consists of a simplified burnup model for a chain of 18 actinide isotopes and a fuel cycle model to evaluate high-level waste (HLW) generation from the reference ATW plant. Interpolation formulas for effective one-group cross sections as a function of the actinide mass fraction have been developed. Three kinds of HLW generation were considered: (a) HLW from uranium separation for light water reactor (LWR) spent fuel, (b) HLW from the partitioning process in multicycle ATW operation, and (c) the last core of the transmuter at the decommissioning of the ATW system. The latter two HLW sources resulting from multicycle ATW operation have been found to be greater than the first source. Potential benefits of ATW deployment have been found to be (a) reduction of the total actinide toxicity by a factor of 48 at the time of waste generation and (b) conversion of the actinide mixture into a more proliferation-resistant configuration, by effective transmutation of 239Pu, 241Am, and 237Np included in the LWR spent fuel. The total actinide radiotoxicity further decreases to 1/260 for the time period of 100 000 yr, which would improve the performance of the Yucca Mountain Repository.
