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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.
Tetsuo Tanabe
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1278-1283
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30586
Articles are hosted by Taylor and Francis Online.
To apply the surface barrier to reduce hydrogen permeation, the influence of the surface barrier on both the permeation and retention has been investigated considering physical and chemical stability of the barrier in fusion environment. Since energetic hydrogen from the plasma not only impinges directly into subsurface but also removes the front surface barrier, only the back surface barrier works reliably . Oxides, carbide and nitride are candidates as the barrier but their mechanical as well as chemical stability is an important concern, because very large thermal gradient and thermal cycling in fusion environment could enhance the crack initiation and exfoliation of the barrier Therefore an appropriate barrier which is stable under a particular operating condition must be developed The most reliable way to reduce the permeation is to use a metallic layer, but it must be rather thick. It should be noted that the back surface barrier to suppress the permeation inevitably increases the retention Therefore an optimization between the permeation decrease and retention increase is necessary. An alternative way to reduce the plasma or ion driven permeation is to decrease the recombination coefficient at the back surface However, large uncertainty in the observed recombination coefficients does not allow us to rely on the recombination limited process and further work is needed.