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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.
Laila A. El-Guebaly, Mohamed E. Sawan
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 881-886
ITER Nuclear Design | doi.org/10.13182/FST89-A39805
Articles are hosted by Taylor and Francis Online.
The shield design of ITER is required to meet both magnet protection requirements and safety-related criteria. Although the W provides excellent magnet protection, its high specific decay heat caused some concern in case of an accident. A trade study was carried out in which W is replaced by steel in the high neutron flux zones of the inboard shield and the sensitivity of the machine size, cost, and magnet damage to such change was determined. Satisfying the 1019 n/cm2 fast fluence limit for the magnet, the direct cost is essentially the same for the steel and W shields, although the steel shield is 0.1 m thicker. The 0.55 m thick inboard shield of ITER is configured in 3 main layers: a 0.05 m Be layer, followed by a 0.18 m steel layer, then a 0.18 m W layer. Five coolant channels, each 0.01 m wide, are properly distributed across the shield. About 0.1 m thick layer of aqueous Li salt solution at the back of the shield was found necessary to minimize the damage in the magnet. This design meets the neutronics, safety, and thermal hydraulics requirements and there appears to be no feasible problems associated with it.