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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.
S. Ramakrishnan, N. Greenough, E. Fredd, S. Bernabei, C. Neumeyer
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 830-833
Plasma Fuelingand Heating, Control, and Currentdrive | doi.org/10.13182/FST96-A11963040
Articles are hosted by Taylor and Francis Online.
Lower Hybrid Current Drive (LHCD) Heating is proposed to be provided for the Tokamak Fusion Test Reactor Advanced Phase (TFTR-AP). The power to be delivered to the plasma is a total additional RF power of 3 MW (4 MW Source Power) at 4.6GHz, divided into two systems of 1.5 MW each. The first system (first phase of the job) is scheduled to be operational in April 1997 and the second system (Second phase of the job) by September 97. (The project is now on hold due to funding limitations). The Reactor is expected to operate for three more years with the additional equipment. It is proposed to utilize used equipment from the Princeton Beta Experiment (PBX) tokamak, Massachusetts Institute of Technology (MIT), and Lawrence Livermore National Laboratory (LLNL) wherever feasible. Power System equipment is also proposed to be taken on loan from LLNL for the LHCD system. The major concern in the LHCD hardware is driven by the new operating duty cycle. The PBX LHCD system was designed for operation for 500 milliseconds every 300 seconds. The system for TFTR requires operation for 3 seconds every 300 seconds. During the Conceptual Design Phase of LHCD for TFTR, the power system components for Electrical Power System were analyzed to verify whether the equipment can meet the new operational requirements with or without modifications. The Power System is composed of electrical and mechanical systems that convert 13.8 kV prime power to controlled pulsed power required for the LHCD system. The major equipment involved are Circuit Breakers, Auto and Rectifier Transformers, Surge Suppression components, Power Tetrodes, HV Decks, Klystron Amplifiers and Transmission lines. Heat runs are proposed to be conducted for the Power equipment to verify capability. Other components were analyzed to verify their thermal limitations. This paper describes the Electrical Power System components for the Lower Hybrid Current Drive