Soujanya Jana

ORCID: 0009-0002-9633-009X
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Recycling and Waste Management Techniques
  • Microplastics and Plastic Pollution
  • Agricultural Science and Fertilization
  • Heat transfer and supercritical fluids
  • Subcritical and Supercritical Water Processes
  • Nanoparticles: synthesis and applications
  • Crop Yield and Soil Fertility
  • Rice Cultivation and Yield Improvement
  • Municipal Solid Waste Management

Ramakrishna Mission Vidyamandira
2024

Ramakrishna Mission Vivekananda Educational and Research Institute
2024

Bhabha Atomic Research Centre
2015-2018

Conceptual molten salt breeder reactor (MSBR) is under development in Bhabha Atomic Research Centre (BARC) with long-term objective of utilizing abundant thorium available India. It based on salts, which acts as fuel, blanket, and coolant for the reactor. LiF–ThF4 (77.6–22.4 mol %) proposed a blanket Indian MSBR. A laboratory scale natural circulation loop (MSNCL) named active fluoride (MAFL) has been setup thermal-hydraulic, material compatibility, chemistry control studies. Steady-states...

10.1115/1.4036027 article EN Journal of Nuclear Engineering and Radiation Science 2017-02-27

Abstract A field experiment was conducted during the rabi (winter) seasons of 2017–2018 and 2018–2019 at Central Research Farm under Bidhan Chandra Krishi Viswavidyalaya, West Bengal, India, to study effects planting techniques, irrigation regimes, nursery bed management on growth, yield, nutrient dynamics, water productivity, economics summer rice (cv. Shatabdi) production. The performed in a strip-split plot design with twelve treatment combinations, which were replicated three times....

10.1007/s43621-024-00300-8 article EN cc-by Discover Sustainability 2024-05-31

Abstract Natural circulation systems find extensive applications in industrial engineering systems. One of the is nuclear reactor where decay heat removed by natural fluid under off-normal conditions. The upcoming designs make use order to remove from core normal operating conditions also. These reactors employ multiple vertical fuel channels with provision on-power refueling/defueling. are relatively simple, safe and reliable when compared forced However, prone encounter flow instabilities...

10.3139/124.110585 article EN Kerntechnik 2016-03-11

10.1615/ihmtc-2017.1540 article IT Proceeding of Proceedings of the 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017) 2018-01-01
Coming Soon ...