Quantification of Zr in simulated dissolver solution of U–Zr fuel by laser-induced breakdown spectroscopy-Reference-Cited by-同舟云学术

Quantification of Zr in simulated dissolver solution of U–Zr fuel by laser-induced breakdown spectroscopy

Published:2024-05-24 Issue:7-8 Volume:112 Page:481-486
ISSN:0033-8230
Container-title:Radiochimica Acta
language:en
Short-container-title:

Author:

Maity Ujjwal Kumar¹,Janardhanan Namitha¹,Periasamy Manoravi¹²

Affiliation:

1. Materials Chemistry & Metal Fuel Cycle Group Indira Gandhi Centre for Atomic Research , Kalpakkam , 603102 , India

2. Directorate of Research and Virtual Education , SRM Institute of Science and Technology , Kattankulathur , 603203 , India

Abstract

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.

Publisher

Walter de Gruyter GmbH

Link

https://www.degruyter.com/document/doi/10.1515/ract-2023-0208/pdf

Reference20 articles.

1. Hofman, G. L.; Walters, L. C.; Bauer, T. H. Metallic Fast Reactor Fuels. Prog. Nucl. Energy 1997, 31, 83–110; https://doi.org/10.1016/0149-1970(96)00005-4.

2. Walters, L. C.; Hofman, G. L. Metallic Fast Reactor Fuels: a Comprehensive Treatment. Mater. Sci. Technol. 1994, 10, 1–43.

3. Crawford, D. C.; Porter, D. L.; Hayes, S. L. Fuels for Sodium-Cooled Fast Reactors: US Perspective. J. Nucl. Mater. 2007, 371, 202–231; https://doi.org/10.1016/j.jnucmat.2007.05.010.

4. Lee, K. S.; Kim, I. Y.; Lee, W.; Yoon, Y. S. Effect of Zr Thin Film on Zr Foil as a FCCI Barrier between Lanthanide (La-Ce) and Clad Material. Met. Mater. Int. 2015, 21, 498–503; https://doi.org/10.1007/s12540-015-4433-7.

5. Harp, J. M.; Chichester, H. J.; Capriotti, L. Post Irradiation Examination Results of Several Metallic Fuel Alloys and Forms from Low Burn-Up AFC Irradiations. J. Nucl. Mater. 2018, 509, 377–391; https://doi.org/10.1016/j.jnucmat.2018.07.003.