C.P. Kaushik

ORCID: 0000-0003-2709-2489
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About
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Research Areas
  • Radioactive element chemistry and processing
  • Nuclear materials and radiation effects
  • Glass properties and applications
  • Chemical Synthesis and Characterization
  • Luminescence Properties of Advanced Materials
  • Extraction and Separation Processes
  • Nuclear Materials and Properties
  • Graphite, nuclear technology, radiation studies
  • Recycling and utilization of industrial and municipal waste in materials production
  • Nuclear and radioactivity studies
  • Radioactive contamination and transfer
  • Radioactivity and Radon Measurements
  • Analytical chemistry methods development
  • Lanthanide and Transition Metal Complexes
  • Thermal and Kinetic Analysis
  • Graphene research and applications
  • Advanced Thermoelectric Materials and Devices
  • Nuclear Physics and Applications
  • Ocular Oncology and Treatments
  • Concrete and Cement Materials Research
  • Metallurgical Processes and Thermodynamics
  • X-ray Spectroscopy and Fluorescence Analysis
  • Ionic liquids properties and applications
  • Recycling and Waste Management Techniques
  • Nuclear reactor physics and engineering

Homi Bhabha National Institute
2015-2024

Guru Jambheshwar University of Science and Technology
2011-2024

Bhabha Atomic Research Centre
2014-2023

Bhabha Atomic Research Center Hospital
2007-2023

Indira Gandhi Centre for Atomic Research
2021

University of Mumbai
2020

Department of Atomic Energy
2019

Waste Management (United States)
2007

A sodium barium borosilicate glass matrix with a higher solubility of sulfate has been developed recently at Bhabha Atomic Research Centre for vitrification bearing high‐level nuclear waste. We report here the studies carried out to understand influence ion on three‐dimensional network. Experiments were base samples loaded varying amounts SO 4 2− (0–5 mol%). Phase separation revealed that as much 3 mol% can be within without any phase separation, however, beyond this limit BaSO (barite)...

10.1111/j.1551-2916.2008.02773.x article EN Journal of the American Ceramic Society 2008-12-01

10.1016/j.nimb.2011.06.009 article EN Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms 2011-06-29

Nuclear Power Programme in India is based on "closed fuel cycle". Closed cycle involves reprocessing and recycling of Spent Fuel (SNF) coming out nuclear reactors. During reprocessing, uranium &plutonium, constituting bulk the SNF are separated subsequently recycled. The remaining small portion constitutes high level radioactive waste containing most fission products minor actinides. A three-step strategy involving immobilization, interim storage followed by ultimate disposal has been...

10.1016/j.mspro.2014.10.004 article EN Procedia Materials Science 2014-01-01

LIBS (Laser Induced Breakdown Spectroscopy) for simultaneous multielement quantification of nuclear waste glass using a spectral modification based PLSR approach.

10.1039/c5ja00372e article EN Journal of Analytical Atomic Spectrometry 2015-01-01

Understanding the role of V 2 O 5 within borosilicate glass matrices is important for development novel toward immobilization sulfate containing high‐level nuclear wastes. Present investigation shows, sodium barium matrix can be homogeneously added up to mol% and beyond which it separates out into three phases, example, (i) silica (ii) Barium (Ba) – Vanadium (V) oxide, (iii) matrix. 29 Si MAS NMR (Nuclear Magnetic Resonance) studies samples show that below addition, silicate network...

10.1111/jace.13303 article EN Journal of the American Ceramic Society 2014-10-27
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