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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.
T. H. Trumbull, D. R. Harris
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 350-360
Technical Paper | Radiation Protection | doi.org/10.13182/NT06-A3739
Articles are hosted by Taylor and Francis Online.
The effect of material homogenization on the calculated gamma-ray dose rate was studied for several arrangements of typical pressurized water reactor (PWR) spent fuel pins in an air medium using the Monte Carlo code MCNP. The models analyzed increased in geometric complexity, beginning with a single fuel pin; progressing to small lattices, i.e., 3 × 3, 5 × 5, and 7 × 7 fuel pins; and culminating with a full 17 × 17 pin PWR bundle analysis. The fuel pin dimensions and compositions were taken directly from a previous study, and efforts were made to parallel this study by specifying identical flux-to-dose functions and gamma-ray source spectra.The analysis shows two competing components to the overall effect of material homogenization on the calculated dose rate. Homogenization of pin lattices tends to lower the effect of radiation channeling but increase the effect of source redistribution. Depending on the size of the lattice and the location of the detectors, the net effect of material homogenization on the dose rate can be insignificant, or it can range from a 6% decrease to a 35% increase relative to the detailed geometry model.
