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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.
Kurt Borrass
Fusion Science and Technology | Volume 16 | Number 2 | September 1989 | Pages 172-184
Technical Paper | Plasma Engineering | doi.org/10.13182/FST89-A29146
Articles are hosted by Taylor and Francis Online.
Contrary to the assumptions made in previous estimates, next-generation tokamaks are now characterized by lower beta, elevated temperatures (current drive, density limit), and imperfectly reflecting walls (graphite, ceramics). All these features lead to an enhancement of cyclotron radiation losses in relation to, for instance, bremsstrahlung losses. The impact of cyclotron radiation losses on the performance of next-generation tokamaks is rediscussed in the light of these effects. Graphite and silicon carbide (SiC) are considered as typical candidates for weakly and strongly absorbing wall materials, respectively. Various Next European Torus configurations and operation scenarios are taken as representative examples to study the problems relating to plasma performance. The physics of microwave absorption in solid media is reviewed, and various graphite and SiC-based solutions are analyzed. The thermomechanical impact of a volumetric load is also discussed. If all these effects are combined (〈T〉 = 15 keV, weakly or strongly absorbing wall), bremsstrahlung losses and cyclotron radiation losses become comparable and the latter are no longer negligible. In the case of a strongly absorbing wall, cyclotron radiation losses even exceed bremsstrahlung losses by 50%. Due to the strong temperature dependence, cyclotron radiation losses provide a considerable stabilizing effect on thermal runaway. This may provide full stabilization in the case of a favorable confinement scaling or reduce the growth rate to an extent that simplifies application of active stabilization schemes.