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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.
Ronald J. Onega, Bill M. Su
Fusion Science and Technology | Volume 2 | Number 4 | October 1982 | Pages 667-686
Technical Paper | Blanket Engineering | doi.org/10.13182/FST82-A20806
Articles are hosted by Taylor and Francis Online.
Calculations of the steady-state neutron, photon, and temperature distributions as well as the transient thermal distribution following a major plasma disruption (MPD) in the first wall and blanket region of an engineering type of controlled thermonuclear reactor was made. A canister blanket design was considered and both the incident neutron and secondary gamma-ray heating were used in calculating the volumetric heat source rate. An average value of the volumetric heat source rate was calculated to be ∼0.5 MW/m3 and the neutron wall loading was 2. 38 MW/m2. After steady-state conditions were obtained, major plasma disruption times of 10 and 24 ms were assumed for the transient calculations. For each case, a constant velocity model was assumed for the surface heat flux impinging on the first wall during an MPD. Neutronic studies using the ANISN code provided volumetric heat source rates that were used to do the thermal analysis. With these volumetric heat source rates obtained, a heat conduction code, HEATING5, was run for the steady-state temperature distribution. Using the steady-state temperature distribution as an initial condition, HEATING5 was run again for the transient thermal study, which included the surface heat flux due to the disruption, together with a volumetric heat source rate resulting from the eddy currents induced in the wall following an MPD. Results show that there is a possibility of melting portions of the first wall if the disruption time of 10 ms is used, while no melting is possible for the 24-ms case; however, a maximum transient temperature of ∼1000°C on the first wall does occur. The temperature in the blanket region remained the same as before the MPD since the transient takes place so rapidly that the effects were felt most by the first wall. The average number of abortions allowed before failure of the first wall was 200 thermal cycles for the 24-ms case.