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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.
Mansur A. Alammar, Ronald V. Furia, Jimmy H. Chin, Chandrakant B. Mehta
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 353-366
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34148
Articles are hosted by Taylor and Francis Online.
The development of the Oyster Creek RETRAN licensing model is presented. A three-step program was followed, namely:Step 1. Model benchmark against start-up tests: The objective here was to assure model stability and to qualify different segments of the model against plant data. A best-estimate model was thus established at this stage. Nine start-up tests were used.Step 2. Assurance that the model has built-in conservatism with respect to the reload transients it is designed to analyze. Here, a sensitivity study was carried out on a number of parameters for the limiting reload transient for Oyster Creek [turbine trip without bypass (TTWOB)]. The impact on the critical power ratio was used as the primary measure. Results from this study were used in establishing a conservative set of parameters, an uncertainty margin, and a proper choice of code options. The implementation of these results established the licensing model.Step 3. Testing the licensing model response against vendor’s analyses for typical reload transients, namely, TTWOB, main steam isolation valve closure without scram, and feedwater controller failure in maximum demand. This methodology has been submitted for U.S. Nuclear Regulatory Commission approval.