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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.
Min Lee, Chen Tsung Fan
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 43-57
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34702
Articles are hosted by Taylor and Francis Online.
Responses of a large, dry pressurized water reactor (PWR) containment in a station blackout sequence are analyzed with the CONTAIN, MARCH3, and MAAP codes. Results show that the predicted containment responses in a station blackout sequence of these three codes are substantially different. Among these predictions, the MAAP code predicts the highest containment pressure because of the large amount of water made available to quench the debris upon vessel failure. The gradual water boiloff by debris pressurizes the containment. The combustible gas burning models in these codes are briefly described and compared. In a station blackout sequence of a large, dry PWR containment, the discrete burning of combustible gases does not occur in the MAAP calculation because of the predicted high steam concentration. A comparison of the one-cell MARCH3 calculation and the six-cell CONTAIN calculation shows that the burning of combustible gases occurs earlier and has a larger impact on containment pressure in the MARCH3 calculation. For the cases analyzed, the simplified MARCH3 calculations always predict a higher containment pressure than the complicated CONTAIN calculations. The results of the CONTAIN calculation show that combustible gas detonation may occur in a local region of a large, dry PWR containment during a station blackout sequence.