Vaibhav Mishra
Postdoctoral position at Department of Physics and Astronomy; Applied Nuclear Physics
- Telephone:
- +46 70 606 20 89
- E-mail:
- vaibhav.mishra@physics.uu.se
- Visiting address:
- Ångströmlaboratoriet, Lägerhyddsvägen 1
- Postal address:
- Box 516
751 20 UPPSALA
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Research
My research is centered around the use of multivariate methods and machine learning in nuclear safeguards of current and future nuclear fuel cycles.
Publications
Selection of publications
- Development of a modeling approach to estimate radiation from a spent fuel rod quiver (2020)
- R&D related to final disposal at Uppsala University (2020)
- Investigating the gamma and neutron radiation around quivers for verification purposes (2019)
- Machine learning in nuclear safeguards (2019)
Recent publications
- Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor (2024)
- Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes (2024)
- Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes (2024)
- Applied nuclear physics in the Alva Myrdal Centre for nuclear disarmament (2023)
- Serpent modelling of pressurized heavy water CANDU reactors (2023)
All publications
Articles
- Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor (2024)
- Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes (2024)
- Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes (2024)
- Statistical analysis of fuel cycle data from Swedish Pressurized Water Reactors and the impact of simplifying assumptions on simulated nuclide inventories (2023)
- Proliferation Related Issues of Sodium-Cooled Fast Breeder Reactors (2020)
- Estimating gamma and neutron radiation fluxes around BWR quivers for nuclear safeguards verification purposes (2020)
- Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept
Books
- Nuclear safeguards directed to the application of multivariate analysis techniques to existing and future nuclear fuel cycles (2023)
- Nuclear Safeguards Assessments For Verification Of Regular And Non-Regular Light Water Reactor Fuel (2021)
Conferences
- Applied nuclear physics in the Alva Myrdal Centre for nuclear disarmament (2023)
- Assessments of design and operational parameter sensitivity towards plutonium production in heavy water reactors (2023)
- Comparison of the physical and operational parameters of the CANDU reactor and the NRX reactor (2023)
- Assessments of radiation emission from molten salt reactor spent fuel: Implications for future nuclear safeguards verification (2023)
- Coincidence spectroscopy for increased sensitivity in radionuclide monitoring (2022)
- Non-proliferation and safeguards activities within the Alva Myrdal Centre for nuclear disarmament (2022)
- A technical view on Pakistan's nuclear weapons programme (2022)
- Research on safeguarding molten salt reactor systems at Uppsala University (2022)
- Prediction of fuel salt composition using fuel data libraries developed for the Molten Salt Demonstration Reactor (2022)
- Neptunium: time for nuclear safeguards? (2022)
- Comparison Of Different Supervised Machine Learning Algorithms To Predict PWR Spent Fuel Parameters (2021)
- The open-source toolbox of the nuclear safeguards data scientist (2021)
- Development of a modeling approach to estimate radiation from a spent fuel rod quiver (2020)
- Investigating the gamma and neutron radiation around quivers for verification purposes (2019)
- Machine learning in nuclear safeguards (2019)
Reports
- Serpent modelling of pressurized heavy water CANDU reactors (2023)
- OPCW as a Model for a TPNW Structure (2022)
- Application of Neural Networks to Nuclear Safeguards (2021)
- Presentation at 10th Serpent User Group Meeting titled "Use of Serpent Monte-Carlo code for development of 3D full-scale models and analysis of spent fuel quivers" (2020)
Other
