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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.
R. Kumazawa, T. Mutoh, K. Saito, T. Seki, H. Kasahara, M. Tokitani, S. Masuzaki, N. Ashikawa, Y. Nakamura, S. Kubo, T. Shimozuma, Y. Yoshimura, H. Igami, H. Takahashi, Y. Takeiri, K. Tsumori, M. Osakabe, K. Ikeda, K. Nagaoka, O. Kaneko, M. Goto, K. Sato, H. Chikaraishi, K. Ida, Y. Nagayama, Y. Zhao, J. G. Kwak, J. S. Yoon, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 524-529
Chapter 10. Ion Cyclotron Range of Frequency Heating | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10839
Articles are hosted by Taylor and Francis Online.
As one of the main objectives of operation of the Large Helical Device (LHD), long-pulse plasma discharge experiments have been carried out using ion cyclotron range of frequency (ICRF) heating power (mainly using a minority heating method). Discharges with electron density ne < 1019 m-3 and Te0 > 1 keV have been sustained with an ICRF heating power around [approximately]1 MW and an electron cyclotron heating power of [approximately]0.1 MW. The total injected heating energy exceeded 1.6 GJ. Many technological improvements were made before undertaking long-pulse plasma discharges, e.g., the installation of a steady-state high-rf power generator and a liquid stub tuner capable of real-time impedance matching. Over the past decade, the achieved pulse length has increased to 1 h. One of the keys to this success was dispersion of the local plasma heat load onto divertors, which was accomplished by cyclically sweeping the magnetic axis inward and outward. Eventually, the plasma terminated due to the penetration of impurities, which originated from the release of thin flakes on the divertor plates. The pulse length was extended by installing new divertor plates with better thermal conduction. A mode conversion heating scenario has been considered as an alternative to the minority ICRF heating scenario; the former may have advantages due to the lack of an ion cyclotron resonance layer in front of the antennas in the mode conversion case.