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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.
S.K. Erents
Fusion Science and Technology | Volume 6 | Number 2 | September 1984 | Pages 453-458
Technical Paper | Selected papers from the Ninth International Vacuum Congress and the Fifth International Conference on Solid Surfaces (Madrid, Spain, September 26-October 1, 1983) | doi.org/10.13182/FST84-A23221
Articles are hosted by Taylor and Francis Online.
Plasmas produced while using the MkII Bundle Divertor on DITE have been studied using a combined Langmuir/heat flux probe technique. Ion saturation currents and deposited powers to bolometers facing both the ion and electron drift directions have been measured. A substantial depression of the ion flux on the ion side is recorded, which has been explained by the shorter connection length to the divertor target plate. Radial profiles of electron temperature Te, ion temperature Ti, and local plasma density, ne have been calculated from the measurements. These are time resolved and have been studied both before and during neutral beam injection. E-folding lengths for deposited power of ∼ 1.0cm have been measured, but those for ion and electron temperature are much longer. Calculated values of Ti range from 50 to a few hundred eV, those for Te are an order of magnitude lower. An estimate of carbon limiter sputtering has been made which suggests that for the present discharge conditions (plasma current 150 kA, central density 1.5 – 3 × 1019 m−3), the sputtering rises with increasing density during neutral injection, although a fall in Ti is calculated.