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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.
Qiyang Hu, Shahram Sharafat, Nasr M. Ghoniem
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 574-578
Technical Paper | The Technology of Fusion Energy - High Heat Flux Components | doi.org/10.13182/FST07-A1550
Articles are hosted by Taylor and Francis Online.
During Helium implantation or generation in finite geometries, space dependent parameters and features affect Helium transport through the material. Conventional kinetic rate-theory models assume strictly homogeneous field parameters and as such can not directly resolve space dependent phenomena of helium transport. The current work outlines a new approach to simulate space-dependent helium transport during irradiation in finite geometries. The model and the numerical code, called HEROS, are described and applied to simulate typical IFE relevant helium implantation conditions. A case study using the HAPL IFE reactor design is used to demonstrate the capabilities of the HEROS code. It is shown that the HEROS code is capable of simulating very complex transient and space dependent Helium transport in finite geometries, including the simultaneous transient production of defects and space- and time-dependent temperature and temperature gradients. Space dependent nucleation and growth of helium bubbles during implantation are modeled along with the impact of biased migration and coalescence of Helium bubbles.
