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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.
Jean Johner
Fusion Science and Technology | Volume 59 | Number 2 | February 2011 | Pages 308-349
Technical Paper | doi.org/10.13182/FST11-A11650
Articles are hosted by Taylor and Francis Online.
The HELIOS zero-dimensional code (Version 1.0) is described in detail in the case of deuterium-tritium (D-T) plasmas.The part of the code described solves in a self-consistent way the thermal equilibrium equation of a D-T thermonuclear plasma coupled to the conservation equation of the helium ash with a He*/E = const. constraint.Prominent features of the modeling are the following: description of any type of last closed magnetic surface (LCMS) by means of four portions of conics; exact closed form expressions for the poloidal surface, plasma volume, plasma surface, and LCMS length; exact surface and volume integration (for arbitrary aspect ratio) in the approximation of magnetic surfaces similar to the LCMS; parabolic type density profile and two-parameters temperature profile, both with pedestals and finite values at the separatrix; line radiation of light impurities calculated from tabulated radiative power loss functions; scalings for the pedestal temperature, L-H transition, and confinement time; modeling for the divertor thermal load; self-consistent radial build modeling for the plateau duration calculation; and detailed power plant thermal balance.Applications to ITER and DEMO operation and to inductive reactor design are given.
