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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.
Kazunori Isozaki, Takashi Ashida, Kouzou Sumino, Satoru Nakai
Nuclear Technology | Volume 150 | Number 1 | April 2005 | Pages 56-66
Technical Paper | Sodium Technology | doi.org/10.13182/NT05-A3605
Articles are hosted by Taylor and Francis Online.
The purpose of the MK-III program is to upgrade the irradiation capability of the liquid sodium-cooled experimental fast reactor JOYO. As a result, the neutron flux density of the core was increased, and the reactor thermal power was increased to 140 MW(thermal) from the originally designed 100 MW(thermal). To accommodate the increased thermal power, the flow rates of sodium coolant in the primary and secondary systems were increased by 20 and 10%, respectively. Also, all intermediate heat exchangers and dump heat exchangers were replaced with new ones. The replacement of these large sodium components was carried out over an [approximately]1-yr period with both fuel and molten sodium still in the reactor vessel (RV).Major challenges in the replacement were the control of impurity ingress to existing systems and protection from radiation exposure in the high-dose-rate regions inside the containment vessel. During the replacement, the seal bag method, impurity concentration monitoring of cover gas, and low-pressure control of cover gas were applied to prevent damage to existing components and systems, such as the RV, fuel subassemblies, sodium piping, and tanks. The measures taken to reduce the radiation exposure were a lowering of the surrounding dose rate through the use of temporary shielding, shortening of the operation time near the high-dose-rate area by first doing thorough training, and the employment of protection equipment to avoid contamination. The replacement of components was completed without major trouble, and methods applied for the replacement proved to be effective in the operation and maintenance of sodium-cooled reactors.