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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.
Shigefumi Okada, Fuji Kodera, Katsuhisa Kitano, Michiaki Inomoto, Satoru Yoshimura, Mamoru Okubo, Satoshi Sugimoto, Shoichi Ohi, Seichi Goto
Fusion Science and Technology | Volume 43 | Number 1 | January 2003 | Pages 295-298
Field Reversed Configuration and Neutron Sources | doi.org/10.13182/FST03-A11963618
Articles are hosted by Taylor and Francis Online.
Plasmas with field reversed configuration (FRC) are confined in open systems and have extremely high beta value of about 100% and they are one of candidates for an attractive reactor. But, in many cases they are produced in theta pinch apparatus and accessibility of additional heating facilities is poor. In order to solve this problem and to realize density appropriate for neutral beam injection, technology of translation is useful. By the translation, an FRC plasma is ejected out from theta pinch formation region and is translocated into a confinement region. With this translation, experiments related to sustain and control the FRC plasma become to be accomplished. Actually, axial magnetic compression, neutral beam heating and low frequency RF wave heating experiments are carried out on the FRC Injection Experiment (FIX) apparatus.
