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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.
Yoshiyuki Kataoka, Tohru Fukui, Shigeo Hatamiya, Toshitsugu Nakao, Masanori Naitoh, Isao Sumida
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 386-396
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34722
Articles are hosted by Taylor and Francis Online.
To evaluate the heat removal capability of an external water wall-type containment vessel, which is a passive system for containment cooling, thermal-hydraulic behavior in the suppression and outer pools has been examined experimentally. The following results are obtained: 1. A thermal stratification boundary, which separates the pools into an upper high-temperature region and a lower low-temperature region, is observed just below the vent outlet. 2. The natural-convection heat transfer coefficients (HTCs) for the downward and upward flows that appear inside and outside the primary containment vessel wall are measured. These values can be expressed by Nu = 0.13Ra1/3. 3. The condensation HTCs in the presence of non-condensable gas, which affect heat transfer between the wet well and the outer pool, are measured along the long wall. The vertical variations of the condensation HTCs are within 10% of the averaged coefficients, and the averaged coefficients can be expressed by hm = 0.43(ma/ms)-0.8, where hm (kW/m2·K is the condensation HTC and (ma/ms) is the mass ratio of noncon-densable gas and steam. 4. The capability for decay heat removal in the external water wall-type containment vessel for a 600-MW(electric) plant is evaluated based on these results and is found to be large enough.