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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.
In Cheol Bang, Ji Hyun Kim
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 16-27
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9442
Articles are hosted by Taylor and Francis Online.
Nanofluids including metal or metal-oxide nanoparticles have shown improved thermal performance compared to water. Introducing zinc into a water-containing component of the primary system of a boiling water reactor or pressurized water reactor nuclear power plant is known to prevent the deposition of radioactive cobalt and to reduce the possible susceptibility of component materials to corrosion. Also, it is well known that silicon carbide (SiC) is a promising material for advanced reactors. Therefore, preparations of zinc oxide (ZnO) and SiC nanofluids have been used in diverse methods to reduce inconsistency of nanofluid performance. Thermal-fluid characterizations were carried out under the control of the preparation methods. In addition, indirect checks by contact angle measurements of depositions have shown that ZnO and SiC nanofluids as a self-recovering/healing coating solution can contribute to advanced nuclear safety systems in terms of the critical heat flux margin. The results show that more efforts are needed to develop the nanofluid formulation to tailor the desired properties.