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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.
Dragan Mirkovic, David J. Diamond
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 162-174
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34554
Articles are hosted by Taylor and Francis Online.
An accident sequence in a boiling water reactor is studied in which there is a large reactivity insertion caused by the flushing of borated water from the core. This sequence can occur during an anticipated transient without scram after the injection of borated water from the standby liquid control system. The boron shuts down the power, but if there is a rapid depressurization of the vessel (e.g., because of the inadvertent actuation of the automatic depressurization system), large amounts of low-pressure, relatively cold, unborated water enters the vessel causing a rapid dilution and cooling. This study determines whether the reactivity addition caused by this flushing could lead to a power excursion that is sufficient to cause catastrophic fuel damage. Calculations are carried out using the RELAP5/MOD2 computer code under different assumptions regarding timing and availability of lowpressure pumps and with different reactivity coefficients. The results show that the fuel enthalpy rise is insufficient to cause catastrophic fuel damage, although less severe fuel damage might still be possible from overheating of the fuel cladding.