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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.
Dan M. Goebel, Joseph Bohdansky, Robert W. Conn, Yoshi Hirooka, Wai Kwong Leung, Richard E. Nygren, George R. Tynan
Fusion Science and Technology | Volume 15 | Number 1 | January 1989 | Pages 102-107
Technical Paper | doi.org/10.13182/FST89-A25332
Articles are hosted by Taylor and Francis Online.
The results of erosion and redeposition studies of graphite by hydrogen plasma bombardment in the PISCES facility are reviewed. The total erosion yields of several types of graphites have been measured during plasma exposure with ion fluxes of up to 2 × 1018 cm−2·s−1, ion energies of 50 to 200 eV, and sample temperatures of 50 to 950°C. Hydrogen and deuterium plasmas have been used to bombard Poco, ATJ, and pyrolytic graphites, and a “four-directional” carbon-carbon (C-C) composite weave. The erosion rates of all the graphites tested are about equal, suggesting that surface damage by the ion bombardment results in similar erosion yields. The C-C composite weave material showed an increased weight loss during initial exposure, and then equal or lower erosion yields compared to the other graphites. Graphite has a strong ion energy dependence in the maximum chemical erosion yield at a temperature of 500 to 600°C and no energy dependence for the erosion at room temperature. At temperatures above 800°C, the chemical erosion is suppressed and the erosion yield reaches values expected for physical sputtering with thresholds of ∼40 eV for both hydrogen and deuterium. The measured erosion rates demonstrate that chemical sputtering is not significantly suppressed by high-ion fluxes. The net erosion is also reduced by reionization in the plasma and redeposition of hydrocarbons and physically sputtered carbon.