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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.
Dingqing Guo, Chao Chen, Zhen Wang, Jian Lin, Bing Zhang, Daochuan Ge, Zhibin Chen
Fusion Science and Technology | Volume 78 | Number 2 | February 2022 | Pages 103-110
Technical Paper | doi.org/10.1080/15361055.2021.1960089
Articles are hosted by Taylor and Francis Online.
The fusion reactor fueled by deuterium and tritium will generate many neutron activation products, causing occupational exposure and radiation risk. The minimization of occupational radiation exposure (ORE) is one of the safety goals for fusion reactors. However, detailed designs and management schemes are still lacking for fusion reactors, and the ORE evaluations are still well simplified. In this paper, an integrated assessment approach is proposed for fusion reactors at the conceptual or detailed design stage. The core idea is to estimate the ORE by referring to the dose rates and work efforts of mature fission reactors and ITER and modifying the data of these similar systems by a proportional coefficient according to the differences of component scale, operating environment, etc. The results showed that water cooling fusion reactors will generate the highest collective dose of 2635 p-mSv/year, while the PbLi cooling ones come next with about 1684 p-mSv/year and the helium cooling ones are the least. This method will contribute to fusion reactor design, operation, and maintenance optimization at the earlier stages and provide guidance to reduce the overall potential ORE to workers.