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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.
Hiroyasu Mochizuki
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 90-99
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9448
Articles are hosted by Taylor and Francis Online.
This paper describes the heat transfer in intermediate heat exchangers (IHXs) of liquid-metal-cooled fast reactors when the flow rate is low, such as under natural-circulation conditions. Although empirical correlations of heat transfer coefficients for IHXs were derived using test data of the fast reactors Monju and Joyo and of a 50-MW steam generator facility, the measured heat transfer coefficient was very low compared to the well-known correlation for liquid metals proposed by Seban and Shimazaki. The heat conduction (HC) in IHX is discussed as a possible cause of the low Nusselt number. However, the present results show that HC is not significant under natural-circulation conditions, and the HC term in the energy equation can be neglected in the one-dimensional plant dynamics calculation. Simulations relating natural-circulation transients tested at the Monju reactor were conducted using the NETFLOW++ code with the proposed empirical correlations. Good agreement was obtained for long-term behavior.