Spent nuclear fuel contains both uranium (U) and high yield fission products, including strontium-90 (Sr), a key radioactive contaminant at nuclear facilities. Both U and Sr will be present where spent nuclear fuel has been processed, including in storage ponds and tanks. However, the interactions between Sr and U phases under ambient conditions are not well understood. Over a pH range of 4-14, we investigate Sr sorption behavior in contact with two nuclear fuel cycle relevant U(IV) phases: nano-uraninite (UO) and U(IV)-silicate nanoparticles. Nano-UO is a product of the anaerobic corrosion of metallic uranium fuel, and UO is also the predominant form of U in ceramic fuels. U(IV)-silicates form stable colloids under the neutral to alkaline pH conditions highly relevant to nuclear fuel storage ponds and geodisposal scenarios. In sorption experiments, Sr had the highest affinity for UO, although significant Sr sorption also occurred to U(IV)-silicate phases at pH ≥ 6. Extended X-ray absorption fine structure (EXAFS) spectroscopy, transmission electron microscopy, and desorption data for the UO system suggested that Sr interacted with UO via a near surface, highly coordinated complex at pH ≥ 10. EXAFS measurements for the U(IV)-silicate samples showed outer-sphere Sr sorption dominated at acidic and near-neutral pH with intrinsic Sr-silicates forming at pH ≥ 12. These complex interactions of Sr with important U(IV) phases highlight a largely unrecognized control on Sr mobility in environments of relevance to spent nuclear fuel management and storage.
Download full-text PDF |
Source |
---|---|
http://www.ncbi.nlm.nih.gov/pmc/articles/PMC9098169 | PMC |
http://dx.doi.org/10.1021/acs.langmuir.1c02927 | DOI Listing |
Microscopy (Oxf)
January 2025
Faculty of Engineering, Kyushu University, Fukuoka 819-0395, Japan.
Characterizing molten corium-concrete interaction (MCCI) fuel debris in Fukushima reactors is essential to develop efficient methods for its removal. To enhance the accuracy of microscopic observation and focused ion beam (FIB) microsampling of MCCI fuel debris, we developed a three-dimentional FIB scanning electron microscopy (SEM) technique with a multiphase positional misalignment (MPPM) correction method. This system automatically aligns voxel positions, corrects contrast, and removes artifacts from a series of over 500 SEM images.
View Article and Find Full Text PDFInorg Chem
January 2025
Jiangxi Province Key Laboratory of Nuclear Physics and Technology, East China University of Technology, Nanchang 330013, China.
Recycling waste salt in the dry reprocessing of nuclear fuel and reducing electric energy consumption in the electrorefining process are crucial steps toward addressing significant challenges in this field. The present study proposes a novel approach to purify waste salt by selectively adsorbing excessive fission products using 5A molecular sieves (5A), based on the principles of electrorefining, with the ultimate aim of achieving sustainable development in nuclear fuel. First, Lutetium (Lu)-Bi alloy was synthesized through constant potential electrolysis in the LiCl-KCl-LuCl melt, resulting in a 90.
View Article and Find Full Text PDFSensors (Basel)
January 2025
School of Information Science and Technology, ShanghaiTech University, Shanghai 201210, China.
Accurately measuring the thickness of the oxide film that accumulates on nuclear fuel assemblies is critical for maintaining nuclear power plant safety. Oxide film thickness typically ranges from a few micrometers to several tens of micrometers, necessitating a high-precision measurement system. Eddy current testing (ECT) is commonly employed during poolside inspections due to its simplicity and ease of on-site implementation.
View Article and Find Full Text PDFMaterials (Basel)
January 2025
Department of Mechanical Engineering, University of Nevada, Reno, NV 89557, USA.
Fusion-welded austenitic stainless steel (ASS) was predominantly employed to manufacture dry storage canisters (DSCs) for the storage applications of spent nuclear fuel (SNF). However, the ASS weld joints are prone to chloride-induced stress corrosion cracking (CISCC), a critical safety issue in the nuclear industry. DSCs were exposed to a chloride-rich environment during storage, creating CISCC precursors.
View Article and Find Full Text PDFMaterials (Basel)
January 2025
Department of Civil and Environmental Engineering, University of Nevada, Reno, NV 89557, USA.
Spent nuclear fuel (SNF) from the United States' nuclear power plants has been placed in dry cask storage systems since the 1980s. Due to the lack of a clear path for permanent geological repository for SNF, consolidated and long-term storage solutions that use durable concrete and avoid current aging and licensing challenges are becoming indispensable. Ultra-high-performance concrete (UHPC) is a rapidly growing advanced concrete solution with superior mechanical and durability properties that can help realize future resilient nuclear storage facilities.
View Article and Find Full Text PDFEnter search terms and have AI summaries delivered each week - change queries or unsubscribe any time!