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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.
T. Hayashi, M. Yamada, T. Suzuki, Y. Matsuda, K. Okuno
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1015-1019
Analysis and Accountancy | 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-A30539
Articles are hosted by Taylor and Francis Online.
A scaled ZrCo bed ( 25 g tritium capacity of design ) with gas flowing calorimetry system was fabricated to establish the “in-bed” tritium accounting technology to apply to the ITER tritium storage beds. The basic calorimetric characteristics, steady state temperature raise of He gas stream flowing through a secondary coil line fixed in the ZrCo tritide, was measured and correlated with power input by heater to simulate tritium decay heat or with actual tritium storage. The target accuracy is 1 % which means to measure +− 1 gram (0.32 watt) of tritium on 100 g storage. The results shows the good accounting function that the temperature increases of He stream of 4.7 and 96.8 degrees were measured under power input of 0.32 and 8.0 watts, respectively, with good reproducibility. These “in-bed” tritium accounting function was well demonstrated storing a gram level of tritium gas within a few days.