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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.
S. C. Xiao, Jing Zhao, X. Heng, X. Y. Sheng, Z. Zhou, Y. Yang
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 566-572
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-907
Articles are hosted by Taylor and Francis Online.
In this paper, an innovative natural uranium-thorium fuel fusion-fission hybrid reactor (FFHR) design aiming at closed thorium-uranium fuel cycle, and which could operate with high energy gain, fast 233U breeding rate and tritium self-sufficiency, is presented. The reactor consists of two main modules, i.e. natural uranium module and thorium module, which are placed alternately in the blanket’s toroidal direction. Uranium module plays the role of energy generation and neutron multiplication at the initial stage. Excess neutrons are then used to drive the thorium module to breed 233U. After the 233U inventory reaches a certain level, the uranium module is then replaced by new thorium fuel module. The system is transition to the all thorium fueled operating mode. With appropriately selected thorium fuel to water volumetric ratio, the system could then be started by the limited bred 233U. The blanket could reach thorium-uranium closed fuel cycle with high energy gain and tritium self-sufficiency. The system could burn up about 90 tonnes 232Th at the end of 60 years operating.
