Vaibhav Mishra
Postdoktor vid Institutionen för fysik och astronomi; Tillämpad kärnfysik
- Telefon:
- 070-606 20 89
- E-post:
- vaibhav.mishra@physics.uu.se
- Besöksadress:
- Ångströmlaboratoriet, Lägerhyddsvägen 1
- Postadress:
- Box 516
751 20 UPPSALA
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Forskning
Denna text finns inte på svenska, därför visas den engelska versionen.
My research is centered around the use of multivariate methods and machine learning in nuclear safeguards of current and future nuclear fuel cycles.
Publikationer
Urval av publikationer
- 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)
Senaste publikationer
- 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)
Alla publikationer
Artiklar
- 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
Böcker
- 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)
Konferenser
- 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)
Rapporter
- 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)
Övrigt
