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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.
Mark Massie, Benoit Forget
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 207-223
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors | doi.org/10.13182/NT13-A16431
Articles are hosted by Taylor and Francis Online.
This work presents a methodology for determining the optimal neutron energy spectrum for meeting user-specified transmutation objectives. A simulated annealing routine is used to find the optimal neutron energy distribution by iteratively modifying the flux spectrum, performing depletion calculations, and computing the value of the cost function.To demonstrate this methodology, we found optimal flux spectra for transmuting used nuclear fuel (UNF) to maximize proliferation resistance and to maximize repository capacity by minimizing decay heat. Multiple cost functions are evaluated for each of the two objectives. For maximizing proliferation resistance, we determined the optimal spectra for minimizing 239Pu mass, maximizing 238Pu mass, maximizing 240Pu mass, and minimizing the mass ratio of 239Pu to 238Pu and 240Pu. The results of this study show that while both fast and thermal neutrons are useful for reducing the amount of 239Pu, a thermal spectrum is best for rendering plutonium from UNF unusable as weapons material.Optimal spectra for maximizing repository capacity are found for minimizing the time-integrated decay heat generated by the transmuted UNF. This study shows that optimal transmutation of the full UNF vector can reduce the amount of decay heat released over 10 000 yr by [approximately]39% and that even more substantial reductions are possible with transuranic element-only transmutation, which can decrease decay energy by >81%. Furthermore, it is shown that a thermal spectrum is substantially more effective than a fast spectrum for reducing decay heat released by UNF over 10 000 yr, thus increasing the capacity of heat-limited waste repositories. Results such as these provide powerful insight into the complicated energy dependence of transmutation and illustrate this methodology's effectiveness as a scoping tool.