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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.
Robert L. Hirsch, Gerald L. Kulcinski, Doug Chapin, Herman Diekamp
Fusion Science and Technology | Volume 76 | Number 5 | July 2020 | Pages 670-679
doi.org/10.1080/15361055.2020.1766272
Articles are hosted by Taylor and Francis Online.
The Electric Power Research Institute outlined three criteria important for a commercially viable fusion power plant: competitive electric power cost, regulatory simplicity, and public acceptance. In this paper we consider likely U.S. regulatory considerations for deuterium-tritium (D-T) fusion power reactors, relying on existing criteria and past actions by the U.S. Nuclear Regulatory Commission, which has asserted regulatory jurisdiction over U.S. commercial fusion reactors. We begin with consideration of a basic D-T fusion reactor, independent of plasma confinement approach. Because tritium and radioactivity are present, likely regulation will require containment structures and various safety measures for each component. Regulators are certain to require that all nuclear components of the system be housed in an overall containment vessel that must be held at less than atmospheric pressure to contain any leakage of tritium, radioactive corrosion products, radioactive coolant, and activated elements in the air. In addition, regulators are sure to require plant structure and operations that minimize the potential for clandestine plutonium breeding. Next, we add superconducting magnets and a plasma dump (divertor) to the basic system and recognize the small but nonzero probability of those magnets explosively quenching, potentially causing reactor damage and dramatically increasing containment vessel pressure. Finally, we consider ITER as prototypical of a D-T–fueled fusion power reactor. Because ITER-like systems are subject to damaging plasma disruptions, regulators are almost certain to require safeguards against such events significantly damaging first walls and subsystems. Finally, we believe that regulators are not likely to back off significantly in requirements related to the deuterium-deuterium and D3He fuel cycles even though the tritium production and the neutron damage in the latter fuel cycle are significantly below those in a D-T system. However, regulations for p11B and 3He3He fuel cycles are certain to be dramatically less demanding because of the lack of tritium and essentially no neutron production.