BSc @ University of Madras
MSc @ University of Madras
PhD @ University of Madras
69
Scopus Publications
Scopus Publications
In-house design for a glove box adapted LIBS instrument towards radioactive sample analysis U. K. Maity, P. Manoravi, S. Rajeswari, K. Sundararajan Journal of Radioanalytical and Nuclear Chemistry, 2025 An in-house designed coupling of a commercial LIBS instrument with a single-module glove box for handling irradiated nuclear samples is presented in this article. The study includes the details of in-house design for coupling and mechanical integrity tests. An in-house designed liquid sample cell is employed to minimize the quenching effect in LIBS. Two sets of samples, solid (U–Zr oxide pellet) and liquid (Li in aqueous medium with/without U) are used for the feasibility study of the system. LIBS results are discussed in identifying non-overlapping peaks, calibration plots, correlation coefficient, detection limit, precision, and deviation. LIBS data is compared with the results obtained from laser ablation inductively coupled plasma mass spectrometry (LA-ICPMS) and liquid sampling ICPMS for solid and liquid samples, respectively.
Quantification of Zr in simulated dissolver solution of U-Zr fuel by laser-induced breakdown spectroscopy Ujjwal Kumar Maity, Namitha Janardhanan, Manoravi Periasamy Radiochimica Acta, 2024 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.
Determination of 10B/11B in boric acid and B4C using LA-ICPMS Maity Ujjwal Kumar, Namitha Janarthanam, Bavya Pulipaka, Ushalakshmi Kumar, Manoravi Periasamy, Vijayalakshmi Sreenivasan Radiochimica Acta, 2024 Boron isotopic ratio measurement is very important in the nuclear industry because it is used as neutron poison (in the form of boric acid or a B4C pellet) and control rod material (B4C pellet) in nuclear power plants. Since 10B has a higher neutron absorption cross-section, enriched 10B is used in the nuclear industry and the extent of enrichment varies from 50–90 %. Therefore, it is essential to determine the 10B/11B ratio in boric acid and B4C. The prime purpose of the present study is to utilize LA-ICPMS for evaluating 10B/11B ratio both in solution (boric acid) and solid (B4C pellet) without any pre-treatment so that the difficulty in dissolution or powdering process of B4C (one of the hardest materials) can be avoided and the B4C pellet can be reused. The results obtained from LA-ICPMS for the B4C pellet are discussed and compared with the solution ICPMS, TIMS, and LIMS. The solutions of boric acid (natural abundance) and dissolved B4C (natural & ∼67 % enriched isotopic composition) were analyzed by LA-ICPMS and validated by liquid sampling ICPMS data.
Radiochemical and chemical characterization of fuel, salt, and deposit from the electrorefining of irradiated U-6 wt% Zr in hot cells Dwarapudi Bola Sankar, Rajeswari Seshadri, Kalaiyarasu Thirunavukkarasu, Gurudas Pakhui, Jakkula Siva Brahmaji Rao, Suranjan Bera, Balija Sreenivasulu, Kumaresan Radhakrishnan, Periasamy Manoravi, Venkataraman Jayaraman Radiochimica Acta, 2024 Metal fuels are considered as the promising candidates for future fast breeder reactors. Pyro-chemical reprocessing is the ideal method for reprocessing spent metallic fuels due to the inherent process advantages. Electrorefining run was demonstrated in a hot cell facility with irradiated U-6 wt% Zr alloy at 500 °C using LiCl–KCl eutectic melt. In order to understand the behavior of the actinides and various fission products during high-temperature electrolysis, various process streams, viz., irradiated metal alloy fuel, the eutectic salt, and the cathode deposit were analyzed for the uranium, plutonium, and other fission product contents. Various methods employed for characterizing the process streams and the behaviors of some of the fission products during the electrolysis process are highlighted. The major gamma emitting radionuclides present in the irradiated fuel were 106Ru, 125Sb, 134Cs, 137Cs, 144Ce, and 154Eu. During electrorefining, cesium, cerium and europium were oxidized and dissolved in the molten media, whereas ruthenium and antimony remained in the anode basket. A minor contamination of zirconium was found in the cathode deposit.
Room temperature IR detection using pulsed laser deposited vanadium oxide bolometer Proceedings of SPIE the International Society for Optical Engineering, 2002
