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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.
Gian Luigi Fiorini, Guy Marie Gautier, Yves Bergamaschi
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 239-258
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2999
Articles are hosted by Taylor and Francis Online.
A consistent study was conducted on the total or partial elimination of soluble boron within the framework of the French Commissariat à l'Energie Atomique/Nuclear Reactor Directorate/Innovation Program. Three options were studied: maintaining the soluble boron during cold shutdown; soluble boron only for accident conditions; total elimination of soluble boron. The approach used to identify the motivations that guided the studies on soluble boron reduction or elimination is summarized, and the essential results are presented.After a brief presentation of the objectives of these studies and of the results available in the literature, we comment on the safety means in use (for present reactors) as well as the options, of generic nature, which lead to increased safety in future reactors. The implications linked to the use of soluble boron in the coolant are described. The consequences for the reactor are briefly analyzed in terms of demands for reactivity control reinforcement and for the implementation of a functional redundancy.The modifications in the architecture of elementary systems are briefly examined. The systems affected by soluble boron are identified as are the solutions envisaged for the three options. The influence of the control mode, without soluble boron, on the design of the plant is mentioned. The orientations in the design of new mechanisms to minimize the risks associated with rod ejection are also considered.For the moment, only neutronic quantitative assessment has been achieved. Detailed and quantitative studies have not yet been performed on technological issues. The objective of this work is mainly to indicate the current motivations and to generate discussion and debate on the boron-free option.