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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.
Masabumi Nishikawa, Mitsuru Uetake, Ken-ichi Tanaka, Tomofumi Shiraishi
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 717-722
Tritium Processing | 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-A30489
Articles are hosted by Taylor and Francis Online.
The tritium bred in a DT fusion reactor is taken out of its blanket using helium sweep gas. The cryosorption bed using molecular sieves or activated carbon at liquid nitrogen temperature is attractive for recovery of this tritium from the view point of adsorption capacity and pressure of tritium at release. The mass transfer coefficients required to predict the breakthrough curve are discussed in this paper. The surface difiusivity included in one of them is quantitated. Its value is dependent on the adsorption site. The rate controlling step changes with the equilibrium partial pressure of the hydrogen isotope, because the mass transfer coefficient representing the intraparticle diffusion decreases with increasing equilibrium pressure. The mass transfer coefficients in desorption are estimated to be the same as those in adsorption.