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Nuclear fission product
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Keyword
keyword
Nuclear fission product
RIS
0.003
(Research Intensity Score)
Papers
710
Top papers
Local Charge Density Enhancement Strategy in Nitrogen‐rich Covalent Organic Framework for Boosted Iodine Removal From Water
2025 · 21 citations
AGR-5/6/7 Irradiation Experiment Fission Product Mass Balance
2026 · 5 citations
Silicon carbide and its composites for nuclear applications – Historical overview
2019 · 275 citations
IRDFF-II: A New Neutron Metrology Library
2020 · 197 citations
The Repair Station: Weak-Force Transmutation and the Klein Bottle Eigenvalue — Nuclear Waste as the Operator's Queue
2026 · 4 citations
A review of technetium and zirconium extraction into tributyl phosphate in the PUREX process
2022 · 59 citations
High performing composite beads for effective immobilisation of the fission nuclides strontium and caesium
2024 · 12 citations
A machine learning approach to quantify degradation of nuclear fuels and the effects of fission products
2025 · 6 citations
TAF-ID: An international thermodynamic database for nuclear fuels applications
2020 · 106 citations
Newest papers
AGR-5/6/7 Irradiation Experiment Fission Product Mass Balance
2026 · 5 citations
The Repair Station: Weak-Force Transmutation and the Klein Bottle Eigenvalue — Nuclear Waste as the Operator's Queue
2026 · 4 citations
Radiation Characteristics and Safety Assessment of the BN-350 Fast Reactor’s Spent Nuclear Fuel Model Under Long-Term Dry Storage Conditions
2026 · 1 citations
Speciation and radiation stability of Cr and Ln “Grey-Phases” within Cr-doped (Ln,U)O2 spent fuel model materials
2026 · 2 citations
Structural and Microstructural Characterization of Fission Product Phases in MOX Nuclear Fuel for Fast Neutron Reactors
2026 · 2 citations
Preparation and Application Research of Resin Materials Suitable for
2026
Evaluation of neutron-induced independent fission yields for 37 fissioning systems
2026
Determination of the half-Life of 147Nd and absolute gamma-ray emission intensities from the excited states of 147Pm
2026
Leaching Behavior of Cs-137 from Cement-Based Matrices for Immobilization of Irradiated Uranium–Graphite Fuel
2026
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