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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.
Gerhard Windecker, Henryk Anglart
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 49-61
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3185
Articles are hosted by Taylor and Francis Online.
The phase and mass flux distribution is analyzed in the fuel bundle of a boiling water reactor (BWR). The numerical predictions of phase distribution, obtained with the multifield two-phase flow model implemented in a computational fluid dynamics code, are compared with detailed void measurements. The present model takes into account the detailed geometry of the assembly and the spatial distribution of heat sources. The influence of spacers is modeled by introducing pressure loss and turbulence sources in the momentum and turbulence equations, respectively. The model has been applied for simulation of bubbly two-phase flow for both subcooled and saturated nucleate boiling in a seven-rod bundle and a typical BWR fuel assembly. The predictions are in good agreement with tomographic measurements performed in the FRIGG loop at Westinghouse Atom.
