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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.
K. R. Schultz, A. R. Veca, G. A. Deis, P. Y. S. Hsu, R. E. Nygren, H. Herman
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 763-768
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A22952
Articles are hosted by Taylor and Francis Online.
The First Wall/Blanket/Shield (FWBS) Program has the goal to provide the development and testing of FWBS systems for magnetic fusion reactors. Program Element II of this program is to develop the thermal-hydraulic and thermomechanical data base for blanket and shield components. The critical blanket/shield data needs were identified, alternate techniques to simulate fusion neutron bulk heating were evaluated, and a detailed technical plan was developed. The initial focus is on the critical issues of solid breeder blankets. Two single effect scoping tests are currently in progress to determine the heat transfer characteristics and thermomechanical stability of the solid breeder bed. The design of an integral test to simulate all the non-nuclear aspects of the blanket has been completed. Preliminary planning for a fission reactor-based nuclear test has also been done. Future testing will investigate alternate solid breeder blanket materials and configurations and will begin the investigation of the critical MHD effects of liquid metal blanket concepts.
