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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.
T. Morisaki, S. Masuzaki, M. Kobayashi, R. Sakamoto, K. Tanaka, K. Narihara, H. Funaba, Y. Feng, F. Sardei, N. Ohyabu, A. Komori, O. Motojima, LHD Experimental Group, Y. Feng, F. Sardei
Fusion Science and Technology | Volume 50 | Number 2 | August 2006 | Pages 216-221
Technical Paper | Stellarators | doi.org/10.13182/FST06-A1238
Articles are hosted by Taylor and Francis Online.
Confinement improvement of ~20% from the ISS95 scaling law has been observed in the outwardly shifted configuration on the local island divertor (LID) experiment. In the configuration, highly peaked electron density profiles, together with peaked electron temperature profiles, are established with hydrogen pellet injection. A steep density gradient is formed in the internal region near the rational surface of q = 2 in the density decay phase after pellet injection. The plasma stored energy or central beta value increases and reaches its maximum as the density decreases, which is typical behavior of the reheat mode. Because of the increase in the central pressure, a large Shafranov shift is observed in the electron temperature and density profiles measured with a Thomson scattering system, suggesting the formation of the internal transport barrier during the LID discharge. Such better confinement has never been seen in inwardly shifted configurations. The reason for that is discussed taking the energy and particle transport into consideration. Recent results from a modeling study with the EMC3-EIRENE code are also presented.