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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.
S. Chatzidakis, S. Cetiner, H. Santos-Villalobos, J. J. Jarrell, J. M. Scaglione (ORNL)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 714-720
Over 2,000 canisters are being used for dry storage of commercial spent nuclear fuel (SNF) in the United States, and each year, between 150–200 new canisters are loaded. There is evidence that these welded stainless steel canisters are susceptible to stress corrosion cracking (SCC) under certain conditions (1). Undetected crack development may result in a loss of confinement. SCC is very difficult to predict with crack opening displacements of 15–30 ?m, which are much smaller than what can be detected with current visual inspections (~100 ?m) (2, 3). The lack of initial cracks does not preclude formation of cracks in the future. This observation is particularly critical for SCC, which is characterized by a long incubation period, after which crack initiation and growth evolution is depth dependent. If crack growth is rapid, SCC may not be detected in time to prevent the loss of canister confinement without frequent nondestructive examination (NDE) inspections (4).
Proposed NDE techniques include periodic inspections using eddy currents, bulk ultrasonic waves, guided and surface waves, as well as continuous noncontact monitoring methods such as passive acoustic emission. To develop monitoring systems for SCC, sensor requirements must be carefully considered and evaluated with respect to radiation resistance, size, power consumption, defect sensitivity, axial and lateral resolution, signal-to-noise ratio, and scanning time. This paper examines monitoring requirements, and a variety of sensor types are considered and compared against these metrics. This work focuses on detection and characterization of SCC in welded stainless steel canisters placed within concrete overpacks. Potential compromises, advantages, disadvantages, and compatibility with other state-of-the-art and complementary monitoring techniques such as thermographic phosphors are discussed.