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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.
Didier Perrault
Fusion Science and Technology | Volume 75 | Number 5 | July 2019 | Pages 339-344
Technical Paper | doi.org/10.1080/15361055.2019.1594538
Articles are hosted by Taylor and Francis Online.
The decree authorizing the creation of the ITER facility was published on November 9, 2012, with the provisions adopted having been considered mostly acceptable. However, it is the first fusion facility of this kind to require a creation decree and the design of some of the systems had not yet been finalized. Moreover, while some equipment, with their associated safety requirements, are indeed classic and well known, others are uncommon and their safety requirements, although considered acceptable, are requesting justification.
Therefore, the decree was supported by about 200 requests, which have to be met during the facility startup schedule. This paper takes stock of the current situation and presents the current status of the main expected answers, taking into account the design evolution which has been further proposed by the operator (e.g., the new vacuum vessel pressure suppression system, etc.).
Some safety issues have already been considered as solved (the tokamak support design, accident within the neutral beam cell, etc.). Others are estimated not to be completely satisfactory (e.g., explosion within the vacuum vessel). Before moving on to commissioning, a few issues are still pending (detritiation system efficiency, radiation protection, etc.) and additional studies regarding the final design are expected (hot cells, tritium and waste buildings, etc.).