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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.
Per G. Reinhall, Kwanhum Park, Robert W. Albrecht
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 197-204
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT88-A34161
Articles are hosted by Taylor and Francis Online.
The next generation of liquid-metal fast breeder reactors will likely be passively safe designs in that the reactors will be able to survive a loss-of-flow transient without relying on active safety devices. Thermal distortion of the core assemblies is envisioned as one of the most important contributors to the passive negative reactivity feedback required to control the reactor. Development of these reactors requires that the shape of the distorted fuel assemblies be accurately predicted. It is common practice to use beam elements in the modeling of thermally distorted fuel assemblies. However, by using higher order finite element analysis, it is found that the accuracy of such beam element models are unsatisfactory and should only be used with caution. The investigation shows that this lack of accuracy can be largely overcome by a modification of the beam elements such that the moments created by the frictional contact forces are taken under consideration. In addition, investigation of the effect of the fuel pin bundle indicates that the thermal distortion of fuel assemblies can be made significantly more accurate by including the commonly neglected fuel pins.