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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Deep geologic repository progress—2025 Update
Editor's note: This article has was originally published in November 2023. It has been updated with new information as of June 2025.
Outside my office, there is a display case filled with rock samples from all over the world. It contains a disk of translucent, orange salt from the Waste Isolation Pilot Plant near Carlsbad, N.M.; a core of white-and-bronze gneiss from the site of the future deep geologic repository in Eurajoki, Finland; several angular chunks of fine-grained, gray claystone from the underground research laboratory at Bure, France; and a piece of coarse-grained granite from the underground research tunnel in Daejeon, South Korea.
Yiren Lian, Hongchao Sun, Hao Yang, Xiaopeng Song, Xinjing Yang, Shutang Sun, Pengyi Wang, Lei Chen, Yeming Zhu, Guoqiang Li, Jiangang Zhang
Nuclear Technology | Volume 209 | Number 9 | September 2023 | Pages 1398-1404
Research Article | doi.org/10.1080/00295450.2023.2200542
Articles are hosted by Taylor and Francis Online.
In the nuclear fuel cycle, 30 vol % tributyl phosphate/kerosene is always used as the major actinide extractant. However, there is a risk of fire accident during the usage of the solvent solution. It is necessary to investigate solvent fire because of the release of radioactive materials and possible overheating and blocking of ventilation filters. This paper discusses several tests of solvent solution combustion that were carried out to analyze the safety of solvent fire. Parameters such as gas emission of solvent burning, mass loss rate, and production of aerosol were obtained and analyzed. The experimental data obtained in this paper can be useful to develop a method of solvent fire assessment and evaluate a solvent fire accident in a nuclear fuel cycle facility.
