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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.
W. S. Yeung, J. Shirkov, F. Seifaee
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 387-394
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35021
Articles are hosted by Taylor and Francis Online.
The capability of the RELAP5/MOD3 computer code to analyze water hammer transients due to water column rejoining and a water slug propelled by non-condensable gas is investigated. The code-calculated results have been compared with those obtained from simple ideal analytical models. Good agreement is obtained between the calculation and analytical results in the initial period of the transient during which the water column or slug retains its sharp interface and suffers from little breakup or dissipation. As the transient proceeds, the code-calculated hydrodynamic loads are generally less than those implied by the analytical models. This is most likely due to the breakup of the water phase, which is not taken into account in the analytical models. Effects of time step and mesh sizes have also been studied. The results show that the usual Courant time limit applies. Finally, a sample calculation, corresponding to a water hammer transient in a typical Westinghouse four-loop reactor head vent system piping, is presented. The transient is induced by the opening of a relief valve and accelerating a trapped water slug through the pipeline. Hydrodynamic loads (i.e., force-time curves) on various pipe segments have been evaluated by appropriate postprocessing of the transient results. The calculated peak forces at selected pipe segments compare favorably with those estimated from the analytical models.