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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.
Shigeo Numata, Yasuhiko Fujii, Makoto Okamoto
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 466-472
Technical Paper | Safety Environmental Aspect | doi.org/10.13182/FST91-A29387
Articles are hosted by Taylor and Francis Online.
Cleanup of tritiated water in typical reactor-size concrete enclosures is simulated taking into account the soaking of the tritiated water into the concrete. For an enclosure made of concrete with ordinary porosity, the “soaking effect” has little effect on the cleanup time for releases with tritium concentrations of <1 × 108 Bq/m3. If the concrete porosity is reduced to 0.03, the soaking effect has little effect on the cleanup time for a tritium concentration of up to 1 × 109 Bq/m3. An optimum flow rate of between 1 × 104 and 1.5 × 104 m3/h for the tritium removal system minimizes the costs of removal system equipment and facility downtime for releases with a concentration >5 × 108 Bq/m3 in a typical reactor-size enclosure. Estimated total costs to complete the cleanup within 48 and 72 h with these flow rates are within 1.3 times of the minimum total costs. The estimated total costs for a cleanup time of 48 h are comparable to those for a cleanup time of 72 h.