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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.
Robert Gregg, Andrew Worrall
Nuclear Technology | Volume 151 | Number 2 | August 2005 | Pages 126-132
Technical Paper | Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization | doi.org/10.13182/NT05-A3638
Articles are hosted by Taylor and Francis Online.
A study of high-burnup pressurized water reactor (PWR) fuel management schemes extending to 100 GWd/tonne is presented. The Studsvik Scandpower code suite was used to model a Westinghouse three-loop PWR core, and realistic loading patterns were derived. The loading patterns were optimized for minimum power peaking and maximum cycle length using engineering judgment and automated binary shuffles. Gadolinia was found to control power peaking to within current FH design limits up to 70 GWd/tonne, with only a slight deterioration thereafter. The moderator temperature coefficient, boron coefficient, and control rod worth were calculated and shown to fall within existing design limits.An economic analysis was carried out to determine the most economic discharge burnup based on fuel cycle costs only. It was found that the lowest fuel cycle costs were obtained with average discharge burnups between 70 to 75 GWd/tonne (initial enrichments between 6 to 7 wt%).The energy generated per tonne of uranium ore used was calculated and shown to peak between 40 to 60 GWd/tonne. Also, the radiotoxicity generated per GWyr(electric) was calculated for each fuel management scheme and found to reduce considerably with burnup between 100 and 100 000 yr.