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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.
O. Graf, A. Bayer
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 50-71
Technical Paper | Nuclear Safety | doi.org/10.13182/NT91-A35533
Articles are hosted by Taylor and Francis Online.
Realistic probabilistic safety assessment and risk studies for nuclear power facilities and for emergency planning call for detailed knowledge of the shielding properties of buildings. The investigations described here focus on the building types encountered in central Europe, with its high population density. The necessary dose rate calculations are performed with a new combination of the point kernel integration technique (the QAD-CG-E code) and the Sn transport method (the DOT 4.2 code). This procedure seems to be optimal for irregular three-dimensional shielding structures, providing good accuracy and performing a great number of individual calculations. The validity and accuracy of the procedure are checked by Monte Carlo calculations (the SAM-CE code) and by recalculating a U.S. shielding experiment. The evaluation of literature and the examination of data led to a list of 12 building types representative of those in central Europe. The geometries of the buildings are composed of ∼150 to 300 basic geometrical bodies. This is the input for the QAD-CG-E computer code (i.e., combinatorial geometry). Shielding calculations are performed for these 12 building types assuming contamination by 137Cs. The high-rise apartment and row house building types show a good shielding efficiency (a shielding factor <0.1), while the bungalow and prefabricated house offer the lowest shielding value (a shielding factor of 0.3). The other building types have a mean shielding factor value of 0.1. Additional calculations with 131I and 140La show the influence of the gamma energy on the shielding factor. Moreover, gamma fields or spatial dose rate distributions are calculated for a semidetached house, a prefabricated house, and a high rise. The results are presented by isodose lines drawn through vertical and horizontal cross sections of the buildings.