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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.
Karen Colins, Yu Liu, Liqian Li, Kiranpreet Birdee
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 113-121
Technical Paper | doi.org/10.1080/00295450.2017.1411718
Articles are hosted by Taylor and Francis Online.
Proximate to nuclear power plant severe accidents, sustained high levels of gamma radiative flux are perilous not only to human health but also to the functionality of conventional radiation-monitoring devices. Effective accident mitigation presents a significant challenge because the gamma radiation adversely affects the means by which it is measured. Deployments of large numbers of radiation-hardened monitoring devices, required to meet the demands of adequate system reliability and the large spatiotemporal scales associated with such accidents, are expected to be prohibitively expensive. As an affordable alternative, this paper proposes usage of a wireless sensor network (WSN) built with unshielded low-cost integrated circuits (ICs) acting as consumable proportional sensors of gamma radiation dose. Adverse responses of ICs to damaging gamma radiation dose can be characterized statistically, in controlled laboratory experiments. In subsequent field application, responses of individual ICs, transmitted over a WSN to a remote computer, can be translated into local dose measurements using correlations obtained via the laboratory characterization. Experiments to characterize adverse response to radiation dose were performed on multiple complementary metal-oxide-semiconductor–based electrically erasable programmable read-only memory devices in a Gammacell 220 Cobalt-60 Irradiation Unit (60Co source) at the Canadian Nuclear Laboratories. Details of the experiments, data analyses, and a small-scale prototype WSN are discussed in this paper. Outcomes of the experiments a nd analysis support the concept of using low-cost consumable ICs in a WSN to measure high levels of gamma radiation dose associated with nuclear power plant severe accidents.