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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.
Sunil D. Weerakkody
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 139-144
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-39
Articles are hosted by Taylor and Francis Online.
Until the late 1990s, inspection and enforcement practices at the U.S. Nuclear Regulatory Commission (NRC) were minimally influenced by probabilistic risk assessment (PRA) results. In the late 1990s, the NRC noted various shortcomings of the licensee assessment process [commonly known as the systematic assessment of licensee performance (SALP)] established in 1980. For example, the SALP process was found to lack focus on the most safety important issues and was subjective. The resulting new reactor oversight process is a risk-informed performance-based framework that uses PRA insights. Consequently, the NRC set up a significance determination process (SDP) that would rely on the risk significance of performance deficiencies of the licensees. The SDP assesses contributions from both internal events and external events using the best available information. Over the last two to three decades, the NRC has completed the development of high-quality PRA models that are capable of assessing risks due to internal events. Several recent regulatory actions, some of which were prompted by the events at Fukushima, have provided the impetus for the NRC and the licensees to enhance the methods and information related to assessing risks associated with external events such as earthquakes and floods. This paper describes the current status on how the NRC staff uses the best available information to assess risk associated with external events and notes a plethora of regulatory actions that may provide inertia for the development of high-quality models for external events. The paper then points to past trends on how the regulatory actions in the fire PRA area contributed to significant advancements in fire PRA technology and points to tangible evidence on how the same trend has begun in the area of seismic- and flood-related risk assessments.