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Latest News
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.
Shigeru Tanaka, Yoshihiro Ohara, Shin Yamamoto
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 531-539
Technical Paper | Plasma Heating System | doi.org/10.13182/FST91-A29393
Articles are hosted by Taylor and Francis Online.
The concept and the technical bases of a beam profile controller for a neutral beam injector to realize plasma current profile control in tokamak devices are proposed. Beam orbits of ions emitted from the ion source are controlled magnetically by the beam profile controller before entering the neutralizer. By making use of this beam profile control system, a different neutral beam intensity profile can be realized at the torus plasma without changing the neutral beam power level during one pulse of beam injection.
