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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.
A. Robinson, L. El-Guebaly, D. Henderson
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 715-719
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12469
Articles are hosted by Taylor and Francis Online.
Currently, there is an ongoing international effort to develop and characterize W alloys that are suitable for fusion applications. In this report, five key W alloys were examined for the advanced divertor design of ARIES-ACT - the latest ARIES tokamak design. The most promising alloys appear to be W-1.1TiC and W-La2O3. At the end of the divertor lifetime (~4 years), the maintenance dose of these alloys very closely matches those of W with nominal impurities. Unfortunately, even with pure W, the divertor is not clearable, which indicates that it must be recycled or disposed of in a geological repository. The radiation damage and transmutation are expected to degrade the physical properties of any material. The radiation damage level in W is low compared to ferritic steel - a remarkable feature for tungsten. For ARIES-ACT operating conditions, transmutation of W does not appear to present a significant issue.
