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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.
Thomas M. Parker, Richard J. Kohrt, Sue I. Dederer, Larry E. Hochreiter, Walter R. Schwarz, Chon-Kwo Tsai, Michael Y. Young
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 227-237
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A34243
Articles are hosted by Taylor and Francis Online.
Calculations were performed using a best-estimate computer code that determined the estimates of the 50th percentile peak cladding temperature (PCT) (1006 K) and the 95th percentile PCT (1263 K). These calculations included realistic WCOBRA/TRAC predictions of thermal-hydraulic phenomena occurring inside the vessel during upper plenum injection (UPI). The work done in applying realistic thermal-hydraulic methods for pressurized water reactors (PWRs) with UPI represents an important step in the maturation of advanced best-estimate computer codes like WCOBRA/ TRAC because their effect is finally being used in the licensing of operating plants, and their benefits are being used to make those PWRs more flexible and economic to operate.