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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.
Ara Go, Daesik Yook, Kyuhwan Jeong, GyeongMi Kim, GunHee Jung, Ser Gi Hong
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 605-623
Technical Paper | doi.org/10.1080/00295450.2018.1500795
Articles are hosted by Taylor and Francis Online.
The Basic Plan for High-Level Radioactive Waste Management (national WM plan) was established and promulgated, taking into consideration national and international trends on policy and technology development. In order to evaluate the safety for a facility in accordance with the national WM plan, it is essential to evaluate the spent nuclear fuel (SNF) source term. The objective of this study was to analyze Korea SNF characteristics; to propose reference SNF; and to evaluate generation amounts, radioactivity, thermal power, and isotopic composition of SNF in compliance with the national WM plan in order to provide basic information for safety research in Korea. The Automatic Multi-batch ORIGEN Runner for Evaluation of Spent fuel program (AMORES) was developed and used to evaluate inventory, radioactivity, and thermal power. Generation amounts, radioactivity, thermal power, and isotopic composition of SNF for milestones in the national WM plan were evaluated using a pressurized water reactor SNF database (DB) through 2015, and future SNF generation was estimated by taking into consideration the distribution of initial enrichment and burnup for each power plant unit. As a result, radioactivity, thermal power, and isotopic composition at each site in 2015, 2052, and 2082 differed significantly depending on the presence of new nuclear power plants. In addition, a reference SNF was proposed through statistical analysis of the SNF DB in order to utilize it for safety analysis based on various scenarios when actual SNF data cannot be available. In order to perform a more realistic safety assessment, radionuclide inventories using reference SNF and time-integrated SNF nuclide inventories using actual data were compared, and then, the best-fit reference SNF for each site and year was suggested.