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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.
Scott A. Comes, Paul J. Turinsky
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 31-48
Technical Paper | Fuel Cycle | doi.org/10.13182/NT88-A34173
Articles are hosted by Taylor and Francis Online.
A methodology has been developed for determining the family of near-optimum fuel management schemes that minimize the levelized fuel cycle costs of a light water reactor over a multicycle planning horizon. Feed batch enrichments and sizes, burned batches to reinsert, and burnable poison loadings are determined for each cycle in the planning horizon. Flexibility in the methodology includes the capability to assess the economic benefits of various partially burned batch reload strategies as well as the effects of using split feed enrichments and enrichment palettes. Constraint limitations are imposed on feed enrichments, discharge burnups, moderator temperature coefficient, and cycle energy requirements. The methodology, incorporated into a code named OCEON, uses a zero-dimensional reactor physics model and a rapid fuel cycle cost routine to select minimum cost cycling schemes that satisfy all constraints. These candidate schemes are then examined with a two-dimensional nodal reactor physics model to more accurately calculate feed enrichments, batch burnups, and fuel cycle costs. The use of Monte Carlo integer programming to direct the optimization process allows for the determination of a family of low cost schemes from which the fuel manager can select the strategy that best fits his needs.