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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.
Y. Higashizono et al.
Fusion Science and Technology | Volume 55 | Number 2 | February 2009 | Pages 185-190
Technical Paper | Seventh International Conference on Open Magnetic Systems for Plasma Confinement | doi.org/10.13182/FST09-A7010
Articles are hosted by Taylor and Francis Online.
Based on the results of neutral transport simulation using cylindrical mesh-model, the effect of the plasma edge region was investigated in the GAMMA 10 central-cell. 3-dimensional geometry and neutral sources such as gas puffers, limiters, and neutral beam injection are precisely constructed in the mesh-model of the GAMMA 10 central-cell. From the neutral transport simulation in the case of each neutral source, 1/e decay lengths of H-line intensity (H decay length) along with z-axis were evaluated. It was found that H-line intensity calculated by the simulation of the gas puffer #3(GP#3) in mirror-throat region takes a broader profile than that of central-limiter and gas puffer #7(GP#7) around the central mid-plane region because the plasma density is low in mirror-throat and the neutral particles are given near the vacuum vessel, while the neutral particles in the central-limiter are given near the plasma core. The simulation results also revealed that the H-line intensity drastically decrease in the range with interior components. On the other hand, it was clarified that the H-line intensity in no interior component area takes a little reduction because of a large width in plasma edge region.
