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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.
Gary E. Rochau, Charles W. Morrow, Peter J. Pankuch
Fusion Science and Technology | Volume 43 | Number 3 | May 2003 | Pages 447-455
Technical Paper | Fast Ignition Targets and Z-Pinch Concepts | doi.org/10.13182/FST03-A290
Articles are hosted by Taylor and Francis Online.
The Z-Pinch Power Plant (ZP-3) is the first concept to use the results at Sandia National Laboratories' Z accelerator in a power plant application. Assuming high-yield fusion pulses (of 1 to 20 GJ per shot at a rate of 0.1 Hz), we consider a unique shock and energy absorbing system to contain the energy. One concept answers the need for system standoff from the fusion reaction with a replaceable mechanical cartridge manufactured on-site. System studies suggest integrated blanket designs for absorbing the fusion energy, cartridge manufacture of recycled materials, and cartridge installation/replacement to maintain a reasonable duty cycle. An effective system design for ZP-3 requires an integrated blanket to shield the permanent structures from the high-energy neutron flux and strong shock wave, breed tritium, and simultaneously absorb the released fusion energy. We investigate the feasibility of this integrated blanket concept and explore the principles of a containment chamber - a crucible - and the containment mechanisms. An operational cycle is proposed to physically load hardware in 10-s intervals while maintaining operational conditions. Preliminary pressure and shock calculations demonstrate that high-yield inertial fusion energy pulses can be contained if the appropriate energy-absorbing materials are used.