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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
NRC okays construction permits for Hermes 2 test facility
The Nuclear Regulatory Commission announced yesterday that it has directed staff to issue construction permits to Kairos Power for the company's proposed Hermes 2 nonpower test reactor facility to be built at the Heritage Center Industrial Park in Oak Ridge, Tenn. The permits authorize Kairos to build a facility with two 35-MWt test reactors that would use molten salt to cool the reactor cores.
Yang Hong Jung, Hee Moon Kim
Nuclear Technology | Volume 209 | Number 4 | April 2023 | Pages 595-603
Technical Paper | doi.org/10.1080/00295450.2022.2133935
Articles are hosted by Taylor and Francis Online.
The oxide layer of atomized U-Mo particle nuclear fuel was analyzed using the electron probe microanalyzer (EPMA) wavelength dispersive spectroscopy (WDS) image mapping function. The density of the used nuclear fuel was 2.6 gU/cm3 and the burnup was 16.4%. Typically, measurements of the oxide layer of most nuclear fuel specimens that have been irradiated for research and experimental purposes in the Korea Atomic Energy Research Institute HANARO research reactor have been performed using metallographic equipment. But an oxide layer was not observed in the nuclear fuel used in this study. Therefore, we conducted this study to confirm the presence and thickness of the oxide layer using EPMA WDS image mapping analysis. We were able to confirm the existence of the oxide layer, but there were many shortcomings in determining the exact thickness of the oxide layer using only the identified X-ray image mapping. In this paper, we present a way to accurately measure the oxide layer by recalling the derived original X-ray values as Excel data. To accurately analyze the oxide layer derived from the image, a preliminary study was performed using samples taken from an irradiated Zr-2.5Nb pressure tube from a CANDU pressurized heavy water reactor. In the preliminary study, the exact thickness of the oxide layer measured by metallography and the results obtained by measuring the thickness of the oxide layer with Excel data obtained by X-ray mapping were compared, inferred, and applied to this study. In this study, a method of accurately measuring the thickness of an oxide layer using Excel data obtained by EPMA WDS image mapping of the oxide layer of plate-type fuel, which was not confirmed using metallography equipment, is described in detail.