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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.
Toshio Wakabayashi, Katsuro Takahashi, Tsutomu Yanagisawa
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 14-25
Technical Paper | Kiyose Birthday Anniversary Special / Nuclear Fuel Cycle | doi.org/10.13182/NT118-14
Articles are hosted by Taylor and Francis Online.
Systematic parameter studies were implemented to investigate the basic characteristics [plutonium and minor actinide (MA)-burning rate, burnup reactivity loss, Doppler coefficient, sodium void reactivity, maximum linear heat rate, etc.] of plutonium and MA-burning fast reactors and also to clarify the feasibility of such plutonium and MA burner fast reactors. Highly enriched mixed-oxide (MOX) fuels and plutonium fuels without uranium were consideredfor plutonium-burning enhancement. It was found that plutonium consumption rates essentially depend on plutonium enrichment. Both burnup reactivity loss and Doppler coefficient are important criteria for highly enriched MOX fuel cores. Cores without uranium were found to consume the plutonium at a very large burnup rate close to the theoretically maximum value of 110 to 120 kg/TW · h(electric). The introduction of UO2 in an internal blanket is effective in enhancing the Doppler coefficient; it causes a minor increase in the sodium void reactivity in nonuranium cores. The MA transmutation in a fast reactor core has no serious drawbacks in terms of core performance, provided that the homogeneous loading method can be employed with a small fraction of MA fuel (∼5 wt%). Fast reactors have a strong potential for burning plutonium and MA effectively.