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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.
Joakim Karlsson, Thomas Elevant
Fusion Science and Technology | Volume 33 | Number 3 | May 1998 | Pages 341-349
Technical Paper | doi.org/10.13182/FST98-A36
Articles are hosted by Taylor and Francis Online.
An heuristic approach has been adopted to obtain empirical scaling formulas for the dependence of neutron emission on predefined machine parameters, such as applied auxiliary heating power, plasma current IP, and toroidal magnetic field BT. The results are intended to be used to predict the neutron emission before each discharge. These formulas are of interest in their own right but more practically can be used as input to control software to pre-set the optimum precollimator apertures for neutron diagnostics such as spectrometers. Formulas have been obtained for data from plasma pulses during the years 1992 and (1994 + 1995), i.e., before and after the divertor installation and major modifications of the Joint European Torus (JET) vessel.Obtained scaling formulas for moderate beam power PNB show neutron emission after installation of the divertor to be lower than before. However, for high beam power, the scaling laws predict as large and even larger neutron emissions for the (1994 + 1995) neutral beam (NB)-heated plasmas as compared to 1992 plasmas. The dependence on radio-frequency (rf) heating power Prf is significantly larger in the scaling laws deduced prior to the divertor phase than after, which implies more efficient heating in 1992. With the exception of combined NB- and rf-heated plasma pulses, the dependence on plasma current has increased moderately after the modifications of JET. For all observations with combined NB and rf heating, the dependence on Prf is quite small, and the neutron production for this category of discharges is dominated by NB heating.A set of scaling laws is found that predicts the neutron emission within a factor of 2, which is consistent with our objective.