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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.
Shunsuke Uchida, Masanori Naitoh, Hiroaki Suzuki, Hidetoshi Okada, Satoshi Konishi
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 252-265
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-152
Articles are hosted by Taylor and Francis Online.
As a result of the mass balance analysis for fission products (FPs) in the contaminated water accumulated in the Fukushima Daiichi nuclear power plant in the aftermath of the accident, it was concluded that the short-term cesium source was 50% of the total amount of cesium accumulated in the reactor, which was estimated with the SAMPSON severe accident analysis code, while the short-term source of tritium was 26% of the total tritium that was released during the UO2 fuel meltdown. The FP concentrations in the contaminated water during the 2 yr since the accident were determined by short-term FP sources, while their saturated concentrations, due to a balance between the release from the reactor and the cleanup, were determined by long-term FP sources. A multinuclei removal system, ALPS, has been operated at the plant to clean up the contaminated water to reduce FP concentrations to a level that is permitted for release to the environment. Tritium concentration in the contaminated water decreased a little during the 2 yr since the accident primarily from dilution by mixing groundwater rather than intentional removal. Industrial-scale removal of tritium from the huge amount of contaminated water is almost impossible using isotopic separation methods. Storage of tritiated water for a long period presents a high risk for leakage to the environment. As the most realistic procedure, the authors propose that the tritium be diluted with plenty of seawater to the natural background level and then be released into the ocean with continuous monitoring at the release point.