Abstract
Estimation of Zr in fresh and irradiated metal alloy fuel is important. The homogeneous dissolver solution represents the fuel composition better compared to a highly heterogeneous solid pellet. The present study employs LIBS to determine Zr in the simulated dissolver solution. Four different compositions of U–Zr samples where the Zr/U ratio varies from 0.04 to 0.18 % are analyzed by LIBS with an in-house designed liquid sample cell. A good correlation coefficient is achieved for the measurements in the calibration plot. The results for identifying non-overlapping peaks, calibration plot, precision, deviation, and detection limit are discussed in detail. Two set of solid samples, an oxide pellet and metal alloy with similar Zr/U composition, are also analyzed by LIBS. The results obtained from these three set of samples are inter-compared, and the reason for getting a better Zr/U intensity ratio for a dried coating of sample on aluminium for a given composition is explained.
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Research ethics: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission. Ujjwal Kumar Maity – conceptualize, experiment, data analysis, manuscript writing, editing; Namitha Janardhanan – experiment, data analysis, manuscript writing, editing; Manoravi Periasamy – original idea, manuscript editing.
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Competing interests: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: The raw data can be obtained on request from the corresponding author.
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© 2024 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Preface
- NUCAR-2023: Foreword
- Research Articles
- Theoretical analysis of light and heavy-ion induced reactions: production of medically relevant 97Ru
- Excitation functions of alpha-particle induced nuclear reactions on nat Sn
- Non-destructive assay of plutonium in absence of gamma-ray spectrometry
- Catalytic destruction of oxalate in the supernatant stream generated during plutonium reconversion process
- Quantification of Zr in simulated dissolver solution of U–Zr fuel by laser-induced breakdown spectroscopy
- Radiochemical and chemical characterization of fuel, salt, and deposit from the electrorefining of irradiated U-6 wt% Zr in hot cells
- Zirconium sponge production: an integrated approach for chemical characterization of process intermediates using ICP-OES
- Determination of 10B/11B in boric acid and B4C using LA-ICPMS
- Evaluating sustainability of Bhuj aquifer system, Western India using nuclear dating techniques
- Nanocrystalline Ce(OH)4-based materials: ruthenium selective adsorbent for highly alkaline radioactive liquid waste
- Production and radiochemical separation of 68Ge from irradiated Ga–Ni alloy target in 30 MeV cyclotron
- Preparation of [64Cu]Cu–NOTA complex as a potential renal PET imaging agent using 64Cu produced via the direct activation route
- Total chemical synthesis of PSMA-617: an API for prostate cancer endotherapeutic applications
- Rapid screening technique for gross α and gross β estimations in aqueous samples during radiation emergency
- Development of Dy3+ doped lithium magnesium borate glass system for thermoluminescence based neutron dosimetry applications
Articles in the same Issue
- Frontmatter
- Preface
- NUCAR-2023: Foreword
- Research Articles
- Theoretical analysis of light and heavy-ion induced reactions: production of medically relevant 97Ru
- Excitation functions of alpha-particle induced nuclear reactions on nat Sn
- Non-destructive assay of plutonium in absence of gamma-ray spectrometry
- Catalytic destruction of oxalate in the supernatant stream generated during plutonium reconversion process
- Quantification of Zr in simulated dissolver solution of U–Zr fuel by laser-induced breakdown spectroscopy
- Radiochemical and chemical characterization of fuel, salt, and deposit from the electrorefining of irradiated U-6 wt% Zr in hot cells
- Zirconium sponge production: an integrated approach for chemical characterization of process intermediates using ICP-OES
- Determination of 10B/11B in boric acid and B4C using LA-ICPMS
- Evaluating sustainability of Bhuj aquifer system, Western India using nuclear dating techniques
- Nanocrystalline Ce(OH)4-based materials: ruthenium selective adsorbent for highly alkaline radioactive liquid waste
- Production and radiochemical separation of 68Ge from irradiated Ga–Ni alloy target in 30 MeV cyclotron
- Preparation of [64Cu]Cu–NOTA complex as a potential renal PET imaging agent using 64Cu produced via the direct activation route
- Total chemical synthesis of PSMA-617: an API for prostate cancer endotherapeutic applications
- Rapid screening technique for gross α and gross β estimations in aqueous samples during radiation emergency
- Development of Dy3+ doped lithium magnesium borate glass system for thermoluminescence based neutron dosimetry applications