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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. Gervasini, F. Reiter
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 30-40
doi.org/10.13182/FST95-A11963802
Articles are hosted by Taylor and Francis Online.
Imperfectness of magnetic confinement in tokamak devices leads to interactions of plasma particles and radiation with the first walls and plasma facing components of fusion reactors. The most important processes are discussed. Special emphasis is given to the implantation and transport of hydrogen isotopes in solid materials.
One of the main concerns of hydrogen-material interaction is the determination of hydrogen recycling from the inner surface of the first wall, of hydrogen inventory in and hydrogen permeation through the wall of a fusion reactor. Numerical codes have been developed to calculate these properties. Hydrogen-material interaction parameters which are code input data are discussed. Some results of hydrogen isotopes inventory, recycling and permeation calculations in the next step fusion reactor ITER are presented, their accuracy is affected by the availability of data on trapping and surface processes.