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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.
Thomas Holschuh, Nicolas Woolstenhulme, Benjamin Baker, John Bess, Cliff Davis, James Parry
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1346-1353
Technical Paper | doi.org/10.1080/00295450.2018.1559712
Articles are hosted by Taylor and Francis Online.
The Transient Reactor Test (TREAT) facility restarted transient operations in 2018 and has met or exceeded expectations for reactor experiments. TREAT’s flexibility in power shaping provides the ability to prescribe a variety of operating conditions for test specimens, including shaped transients, steady-state irradiations, natural pulses, and clipped pulses, to deliver the necessary energy deposition and energy deposition rate. The initial operations following the TREAT restart were designed to mimic historical operations to confirm TREAT’s capability. Then, studies were performed to evaluate the minimum pulse width possible in the facility as well as reactor power profiles characteristic of a loss-of-coolant accident (LOCA); both were achieved with excellent results.
This paper highlights the following:
1. The TREAT facility has been restarted to resume nuclear fuel safety research.
2. Initial reactor operations have mimicked historical operations.
3. A minimum pulse width has been achieved by control rod reinsertion during pulse.
4. Power profiles characteristic of a LOCA accident were performed.