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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.
G. A. Cottrell, R. Pampin, N. P. Taylor
Fusion Science and Technology | Volume 50 | Number 1 | July 2006 | Pages 89-98
Technical Paper | doi.org/10.13182/FST06-A1224
Articles are hosted by Taylor and Francis Online.
We present calculations of the transmutation of initially pure tungsten first-wall and divertor plasma-facing armor into W-Re-Os alloys in the European Union Power Plant Conceptual Study (PPCS) fusion plant models A, B, and AB. The fusion neutron spectrum was modeled using the MCNP Monte Carlo code including resonance self-shielding effects, and we have calculated the evolution of the W-Re-Os alloy compositions. Trajectories of the alloys in the thermodynamic phase diagram show that the alloys remain in the single body-centered-cubic phase for their service lifetimes. Results for PPCS models A and B with soft neutron spectra show that the first-wall armor transmutes to an end-of-service alloy composition of approximately 91 at.% tungsten, 6 at.% rhenium, and 3 at.% osmium at its rear face. On the plasma-facing side of the tungsten, the effect of neutron shielding is larger. For PPCS model AB, the neutron spectrum is energetically harder, resulting in significantly lower tungsten transmutation rates.