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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.
Y. Watanabe, T.A. Parish, B. Shofolu, W.D. Booth, R. Carrera, N.E. Hertel
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1938-1943
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29625
Articles are hosted by Taylor and Francis Online.
A shielding analysis of the IGNITEX device proposed by the University of Texas as a relatively inexpensive way to obtain an ignited plasmas has been performed. This paper emphasizes the radiation streaming effects on the radiation environment in the IGNITEX machine. The analysis was done by using a three-dimensional Monte Carlo code, MCNP, along with a one-dimensional discrete ordinate code and simple analytical formulas. The results show that the streaming effect on the global radiation in the test cell is not significant. The vacuum and maintenance penetrations, in particular, straight ducts, increase the radiation level at and near the outlet of the ducts considerably. The vacuum fuel processing and fueling rooms should be specifically shielded from the test cell. Access during the pulses must be limited since the radiation level in these areas is very high during D-T burning pulses because of the radiation streaming from the test cell.
