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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.
V. Subramanian, R. Baskaran, J. Misra, R. Indira
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 83-92
Reactor Safety | doi.org/10.13182/NT11-A12544
Articles are hosted by Taylor and Francis Online.
In core disruptive accident conditions of sodium-cooled fast reactors, the reactor containment building (RCB) is filled with a large amount of sodium aerosols, along with fuel and fission product aerosols. The environmental source term depends on the quantity of aerosols released from RCB, which in turn depends on the quantity of aerosols that remains suspended in the RCB volume. The sodium aerosols are generated by the combustion process, resulting in micrometer-sized aerosols, while fuel and fission product aerosols are generated by vaporization condensation, resulting in nanometer-sized aerosols. To ascertain the behavior of mixed aerosols generated by the different processes, experiments are conducted by generating sodium aerosols and nonradioactive fission product aerosols and then studying their behavior in a closed vessel. The study includes (a) the initial size distribution of CeO2 and SrO2 aerosols, (b) the behavior of suspended mass concentration as a function of time, and (c) the behavior of suspended number concentration as a function of time. The initial size of the sodium combustion aerosols is [approximately]1.0 m, whereas the initial size of the fuel and fission product aerosols is nanometer sized ([approximately]30 nm). In the context of the behavior of the two different-sized aerosols, sodium aerosol behavior dominates the overall suspended mass concentration of the system. The rate of change of number concentration exhibits two regions. The timescale involved for the Brownian coagulation region is found to be [approximately]80 min for nonradioactive fission product aerosols, whereas it lasts only 20 to 30 min when the aerosol system is mixed with sodium aerosols.
