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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.
G. Pierini, B. Spelta, E. Vansant, J. Verbist, A. Viola
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 619-623
Tritium Processing | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25203
Articles are hosted by Taylor and Francis Online.
In thermonuclear fusion reactors, the continuous purification of the plasma exhaust from the impurities present in very low concentrations is required as well as the separation of hydrogen from the DT streams. To obtain this aim, several fixed-bed adsorbers of modified zeolites have been proposed to treat the plasma exhaust stream related to the tritium parameters for the NET Phase II Programme. The adsorption equipment consists of a series of columns containing different types of zeolites characterized by their selective removal of groups of impurities of which those containing tritium are periodically removed by supporting units according to the mass flow sheet proposed and discussed. The final impurity-free hydrogen isotope stream is submitted to gas chromatography for the removal of hydrogen from the other isotopes. Other alternative techniques such as gas chromatography by displacement and pressure swing parametric pumping, are taken into consideration. Major emphasis has been put on the substrates used in the hydrogen isotopic separation system. The characteristics of the most promising zeolite, the (Ca,Na) mordenite small pores (SP), are described. The adsorption isotherms, the kinetics of adsorption for most of the components constituting the plasma exhaust stream are given at different temperatures and pressures, which are indispensable for predicting the performance of the adsorption equipment.