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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. A. Hassan, Parvez Salim
Nuclear Technology | Volume 96 | Number 2 | November 1991 | Pages 139-146
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34600
Articles are hosted by Taylor and Francis Online.
The International Atomic Energy Agency’s third standard problem exercise (SPE-3) is simulated with the RELAP5/MOD2 and RELAP5/MOD3 computer codes. The SPE-3 consists of the simulation of the transient resulting from an 11.9% break in the hot collector of the steam generator (primary-secondary leak) of the PMK-NVH test facility. The predicted scenario is compared with the experimental data. Generally, a reasonable agreement between the code predictions and experimental data is obtained. One important calculated parameter that demonstrates deviation from the data is the break mass flow rate. The RELAP5/MOD2 and RELAP5/MOD3 predictions did not display significant differences. This assessment is a part of an international effort for codes/benchmarks.
