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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.
Marta Velarde, Jose Manuel Perlado
Fusion Science and Technology | Volume 43 | Number 3 | May 2003 | Pages 484-491
Technical Paper | Safety and Environment | doi.org/10.13182/FST03-A295
Articles are hosted by Taylor and Francis Online.
The evaluation of the radiological environmental impact of tritium emission to the atmosphere from inertial fusion energy (IFE) reactors has different chronological phases. In the release primary phase, the important factors are the boundary conditions: atmospheric and geometric grid from the point of emission. The second phase occurs when the tritium is deposited in the ground. This phase is important in order to account for the dosimetric effects of tritium, and it is a key factor in the chronic and collective doses of the population.The final internal irradiation dose is calculated as the addition of doses by ingestion, by inhalation of the primary plume, by absorption on the skin, and inhalation by reemission to the atmosphere.Each of the two chemical forms (HT and HTO) of tritium present in the environment from potential IFE reactor releases contributes in different ways to the most exposed individual and the committed effective dose equivalent (50-CEDE). The HTO presents a much larger percentage of the internal irradiation from inhalation and absorption through the skin than HT. However, in releases where HT represents 100%, the contributions to the total effective dose by ingestion and reemission are important.