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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.
Erbang Hu, Rentai Yao, Zhanrong Gao, Shuxian Wang, Gang Jiang, Jia Yi Chen
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 339-351
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3148
Articles are hosted by Taylor and Francis Online.
A set of deterministic and probabilistic models for estimating the accident washout factor are developed and established based on accident dispersion factor models given by current guidelines. The deterministic washout factor for different time intervals after accident release, the probabilistic washout factor, and the dose corresponding to various pathways are estimated based on the measured meteorological data on the site of a coastal nuclear power plant to be built in the southeastern part of China. The results show that for doses obtained from 0 to 8 h after a design-basis accident release, the external exposure dose from washout deposition given by the deterministic model is ~55% of that from dry deposition and 22% of individual effective dose (except wet deposition dose); the ratios of external exposure dose from washout to that from dry deposition and to effective dose (except wet deposition dose) given by the probabilistic model are ~5.73 and 2.29, respectively.
