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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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Fusion Science and Technology
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Latest News
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.
Jong Woon Kim, Cheol Woo Lee, Young-Ouk Lee, Dong-Won Lee, Seungyon Cho
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 652-656
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-966
Articles are hosted by Taylor and Francis Online.
The discrete ordinates code under development by KAERI uses an unstructured tetrahedral mesh, and can thus be applied to solve the radiation transport in a complicated geometry. In addition, the geometry modeling process has become much easier because computational tetrahedral meshes are generated based on the CAD file by Gmsh. This program has been enhancing its performance and adding functions for each application.
In previous research, it was applied in a neutronics analysis for the Korea Helium Cooled Ceramic Reflector (HCCR) TBM. The total neutron fluxes were compared with the results from MCNPX and showed good agreement.
In this paper, we applied our program to a simplified ITER model which is a 40-degree toroidal segment. The zone averaged total fluxes were compared with those of MCNPX, and total neutron flux distribution was visualized in a three-dimensional system domain.
