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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.
Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 283-301
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3734
Articles are hosted by Taylor and Francis Online.
This paper consists of three parts. The first part presents a mostly thermodynamic comparison of the supercritical carbon dioxide (S-CO2) cycle to helium Brayton, superheated steam, and supercritical steam cycles. Issues that contribute to plant cost are discussed. The second part presents an economic comparison of a gas-cooled reactor coupled to S-CO2 direct, helium Brayton direct, and superheated steam indirect cycles. The results indicate savings of up to 30% if the steam indirect cycle is replaced with the direct S-CO2 cycle. Compared to the helium direct cycle, the savings can reach 15%. The third part describes the optimization and potential of the indirect S-CO2 cycle and the effect of reheating. The indirect cycles of helium to S-CO2 and lead bismuth to S-CO2 are studied to assess the performance of gas-to-gas and liquid metal or liquid salt indirect cycles, respectively. It is shown that although the indirect cycle of helium to S-CO2 is feasible, it poses challenges in the intermediate heat exchanger design and suffers efficiency losses due to the large power consumption of the main circulators. Gas indirect cycles are well suited for liquid metal or liquid salt reactors. Further, the study indicates that employing reheat is economically unattractive for the indirect cycle of helium to S-CO2 because of efficiency reduction from pressure losses in reheaters and interconnecting ducting and additional capital cost. A similar conclusion was also reached for the indirect cycles of liquid metal or liquid salt to S-CO2 even though pumping power is very small. This is because of the additional cost of an intermediate liquid metal (or liquid salt) loop, which needs to be added since it is not possible to place all heat exchangers for reheat inside the reactor vessel.