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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.
D. V. Sherwood, Y. Chikazawa
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 111-119
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3609
Articles are hosted by Taylor and Francis Online.
A particular weakness of the commercial liquid-metal fast breeder reactor is the design of the steam generator (SG). Any small leak in the SG allows the hot sodium (Na) to come into contact with the water/steam, and this results in a violent reaction and SG damage. A secondary circuit is normally used to prevent such reactions causing damage to the reactor core and primary vessel.NNC Ltd. has developed a copper (Cu)-bonded SG system, the objective of which is to provide three separate solid boundaries (two steel and one Cu) between the primary sodium coolant and the water/steam and hence eliminate the possibility of contact between Na and water/steam. The design uses a hot isostatic pressure method of construction to bond all three barriers to aid heat transfer. This highly reliable system allows the elimination of the secondary circuit, greatly reducing the cost of the reactor system and increasing availability.