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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.
Hiroshi Maekawa, Yukio Oyama, Tomoo Suzuki, Yujiro Ikeda, Tomoo Nakamura
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1165-1170
Neutronics and Shielding | doi.org/10.13182/FST83-A23016
Articles are hosted by Taylor and Francis Online.
Angle-dependent neutron leakage spectra above 0.5 MeV from Li2O slab assemblies were measured accurately by the time-of-flight method. The measured angles were 0°, 12.2°, 24.9°, 41.8° and 66.8°. The sizes of Li2O assemblies were 31.4 em in equivalent radius and 5.06, 20.24 and 40.48 em in thickness. The data were analyzed by a new transport code “BERMUDA-2DN”. Time-independent transport equation is solved for two-dimensional, cylindrical, multi-regional geometry using the direct integration method in a multi-group model. The group transfer kernels are accurately obtained from the double-differential cross section data without using Legendre expansion. The results were compared absolutely. While there exist discrepancies partially, the calculational spectra agree well with the experimental ones as a whole. The BERMUDA code was demonstrated to be useful for the analyses of the fusion neutronics and shielding.
