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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.
J. Manuel Perlado, Eduardo Alonso, Kunioki Mima, Sadao Nakai
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1304-1308
Power Plant Design and Technology | doi.org/10.13182/FST96-A11963128
Articles are hosted by Taylor and Francis Online.
The Inertial Fusion Reactor KOYO, proposed by ILE Osaka was completed in its first phase study in 1992, and recent updates including new features have been released up to now. It is based on potentially key achievements in Inertial Fusion Energy (IFE) physics: development to achieve required laser efficiency, implosion stability and gain, pellet fabrication, chamber maintenance, engineering feasibilities, and cost of electricity.
Neutron (target) emission profiles are reported assuming direct drive compressed targets (500 g.cm-3), which have been described with different approaches in stationary transport models. A full three-dimensional description of the reactor has been used to perform the neutronic analysis. Neutron spectra and flucnecs are calculated, and compared with previous one-dimensional results showing the differences in using both approaches. Some figures indicating the neutron flux expected through deep penetrations impinging on the final optics are also presented, representing its coincidence at long distances with the uncollided flux.
The reported consequences are those related to the activation of the materials: shallow land burial (SLB) and recycling. Those radiological responses have been studied for the SiC tubes (components of the blanket), graphite (reflector), and ferritic steel HT-9 (structural wall).
