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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.
Toshio Ida, Shunsuke Kondo, Yasumasa Togo
Fusion Science and Technology | Volume 6 | Number 1 | July 1984 | Pages 64-82
Technical Paper | Shielding | doi.org/10.13182/FST84-A23121
Articles are hosted by Taylor and Francis Online.
A numerical analysis program for radiation transport in axisymmetric toroidal geometry AIDA is developed using the method of direct integration (method of characteristics). The shape of the torus cross section is represented by coupled ellipses with different elongations. Several new techniques, such as a ray-tracing technique in the core plasma region and subdivision of angular mesh cells, are introduced to make the method well adapted to the neutronics analysis of a tokamak. These improvements are illustrated by sample toroidal geometry calculations. To verify the validity of the present program, results of analysis for two sample problems are compared with results of DOT-3.5 as well as those of Monte Carlo calculations. Agreement between the results of AIDA and those of DOT-3.5 becomes better as the quadrature approximation used in DOT-3.5 becomes higher. For the same accuracy, the AIDA code requires only about half as much running time as the DOT-3.5 code for a practical natural lithium blanket system.
