Vaibhav Mishra

Development of a modeling approach to estimate radiation from a spent fuel rod quiver

Elter, Zsolt; Mishra, Vaibhav; Grape, Sophie; Branger, Erik et al.

Ingår i PHYSOR 2020, 2021

• DOI för Development of a modeling approach to estimate radiation from a spent fuel rod quiver
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R&D related to final disposal at Uppsala University: Presentation prepared for the ESARDA Final Disposal WG meeting, Mol Feb 7, 2020

Grape, Sophie; Branger, Erik; Elter, Zsolt; Jansson, Peter et al.

2020

• Ladda ner fulltext (pdf) av R&D related to final disposal at Uppsala University: Presentation prepared for the ESARDA Final Disposal WG meeting, Mol Feb 7, 2020

Investigating the gamma and neutron radiation around quivers for verification purposes

Elter, Zsolt; Mishra, Vaibhav; Grape, Sophie; Branger, Erik et al.

2019

• DOI för Investigating the gamma and neutron radiation around quivers for verification purposes

Machine learning in nuclear safeguards

Grape, Sophie; Branger, Erik; Elter, Zsolt; Jansson, Peter et al.

2019

Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Preston, Markus; Branger, Erik; Fedchenko, Vitaly; Grape, Sophie et al.

Ingår i Nuclear Technology, s. 548-569, 2025

• DOI för Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides
• Ladda ner fulltext (pdf) av Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept

Mishra, Vaibhav; Branger, Erik; Elter, Zsolt; Grape, Sophie et al.

Ingår i Annals of Nuclear Energy, 2025

• DOI för Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept
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Nuclear safeguards assessments of molten salt reactor spent fuel

Mishra, Vaibhav; Branger, Erik; Elter, Zsolt; Grape, Sophie et al.

2024

Researching nuclear reactors deployed at sea from a 3S perspective

Grape, Sophie; Branger, Erik; Josefsson, Henrik; Mishra, Vaibhav et al.

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

Mishra, Vaibhav; Elter, Zsolt; Branger, Erik; Grape, Sophie et al.

Ingår i Data in Brief, 2024

• DOI för Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes
• Ladda ner fulltext (pdf) av Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes

Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Preston, Markus; Branger, Erik; Fedchenko, Vitaly; Grape, Sophie et al.

Ingår i Nuclear Technology, s. 548-569, 2025

• DOI för Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides
• Ladda ner fulltext (pdf) av Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept

Mishra, Vaibhav; Branger, Erik; Elter, Zsolt; Grape, Sophie et al.

Ingår i Annals of Nuclear Energy, 2025

• DOI för Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept
• Ladda ner fulltext (pdf) av Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept

Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes

Mishra, Vaibhav; Elter, Zsolt; Branger, Erik; Grape, Sophie et al.

Ingår i Data in Brief, 2024

• DOI för Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes
• Ladda ner fulltext (pdf) av Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes

Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor

Mishra, Vaibhav; Branger, Erik; Grape, Sophie; Elter, Zsolt et al.

Ingår i Nuclear engineering and technology, s. 3969-3980, 2024

• DOI för Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor
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Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes

Mishra, Vaibhav; Elter, Zsolt; Branger, Erik; Grape, Sophie et al.

Ingår i Data in Brief, 2024

• DOI för Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes
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Statistical analysis of fuel cycle data from Swedish Pressurized Water Reactors and the impact of simplifying assumptions on simulated nuclide inventories

Mishra, Vaibhav; Elter, Zsolt; Branger, Erik; Grape, Sophie

Ingår i Progress in nuclear energy (New series), 2023

• DOI för Statistical analysis of fuel cycle data from Swedish Pressurized Water Reactors and the impact of simplifying assumptions on simulated nuclide inventories
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Estimating gamma and neutron radiation fluxes around BWR quivers for nuclear safeguards verification purposes

Mishra, Vaibhav; Elter, Zsolt; Grape, Sophie; Jansson, Peter et al.

Ingår i Journal of Instrumentation, 2020

• DOI för Estimating gamma and neutron radiation fluxes around BWR quivers for nuclear safeguards verification purposes
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Proliferation Related Issues of Sodium-Cooled Fast Breeder Reactors

Mishra, Vaibhav

Ingår i Connector, s. 32-36, 2020

Nuclear safeguards directed to the application of multivariate analysis techniques to existing and future nuclear fuel cycles

Mishra, Vaibhav

2023

• Ladda ner fulltext (pdf) av Nuclear safeguards directed to the application of multivariate analysis techniques to existing and future nuclear fuel cycles

Nuclear safeguards assessments of molten salt reactor spent fuel

Mishra, Vaibhav; Branger, Erik; Elter, Zsolt; Grape, Sophie et al.

2024

Researching nuclear reactors deployed at sea from a 3S perspective

Grape, Sophie; Branger, Erik; Josefsson, Henrik; Mishra, Vaibhav et al.

2024

Assessments of design and operational parameter sensitivity towards plutonium production in heavy water reactors

Gustavsson, Cecilia; Branger, Erik; Fredriksson, Stina; Hallander, Axel et al.

2023

• Ladda ner fulltext (pdf) av Assessments of design and operational parameter sensitivity towards plutonium production in heavy water reactors

Assessments of radiation emission from molten salt reactor spent fuel: Implications for future nuclear safeguards verification

Mishra, Vaibhav; Branger, Erik; Grape, Sophie; Preston, Markus et al.

2023

Comparison of the physical and operational parameters of the CANDU reactor and the NRX reactor

Gustavsson, Cecilia; Branger, Erik; Grape, Sophie; Mishra, Vaibhav et al.

Ingår i AMC Annual conference 2023, 14-15 June, 2023, 2023, 2023

Applied nuclear physics in the Alva Myrdal Centre for nuclear disarmament: Non-proliferation and safeguards activities

Grape, Sophie; Andersson, Peter; Branger, Erik; Gustavsson, Cecilia et al.

2023

• Ladda ner fulltext (pdf) av Applied nuclear physics in the Alva Myrdal Centre for nuclear disarmament: Non-proliferation and safeguards activities

A technical view on Pakistan's nuclear weapons programme

Gustavsson, Cecilia; Andersson, Peter; Branger, Erik; Grape, Sophie et al.

2022

• Ladda ner fulltext (pdf) av A technical view on Pakistan's nuclear weapons programme

Prediction of fuel salt composition using fuel data libraries developed for the Molten Salt Demonstration Reactor

Mishra, Vaibhav; Branger, Erik; Grape, Sophie; Elter, Zsolt

s. 1-7, 2022

• Ladda ner fulltext (pdf) av Prediction of fuel salt composition using fuel data libraries developed for the Molten Salt Demonstration Reactor

Non-proliferation and safeguards activities within the Alva Myrdal Centre for nuclear disarmament

Grape, Sophie; Andersson, Peter; Branger, Erik; Gustavsson, Cecilia et al.

Ingår i Proceedings of the Symposium on International Safeguards: Reflecting on the Past and Anticipating the Future, 2022

Research on safeguarding molten salt reactor systems at Uppsala University

Mishra, Vaibhav; Branger, Erik; Grape, Sophie; Elter, Zsolt

2022

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Neptunium: time for nuclear safeguards?

Preston, Markus; Branger, Erik; Grape, Sophie; Mishra, Vaibhav

2022

Coincidence spectroscopy for increased sensitivity in radionuclide monitoring

Andersson, Peter; Göök, Alf; Rathore, Vikram; Andersson Sundén, Erik et al.

2022

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Comparison Of Different Supervised Machine Learning Algorithms To Predict PWR Spent Fuel Parameters

Mishra, Vaibhav; Branger, Erik; Elter, Zsolt; Grape, Sophie et al.

2021

Development of a modeling approach to estimate radiation from a spent fuel rod quiver

Elter, Zsolt; Mishra, Vaibhav; Grape, Sophie; Branger, Erik et al.

Ingår i PHYSOR 2020, 2021

• DOI för Development of a modeling approach to estimate radiation from a spent fuel rod quiver
• Ladda ner fulltext (pdf) av Development of a modeling approach to estimate radiation from a spent fuel rod quiver

The open-source toolbox of the nuclear safeguards data scientist

Mishra, Vaibhav; Elter, Zsolt

2021

• Ladda ner fulltext (pdf) av The open-source toolbox of the nuclear safeguards data scientist

Investigating the gamma and neutron radiation around quivers for verification purposes

Elter, Zsolt; Mishra, Vaibhav; Grape, Sophie; Branger, Erik et al.

2019

• DOI för Investigating the gamma and neutron radiation around quivers for verification purposes

Machine learning in nuclear safeguards

Grape, Sophie; Branger, Erik; Elter, Zsolt; Jansson, Peter et al.

2019

Nuclear Safeguards Assessments For Verification Of Regular And Non-Regular Light Water Reactor Fuel

Mishra, Vaibhav

2021

• Ladda ner fulltext (pdf) av Nuclear Safeguards Assessments For Verification Of Regular And Non-Regular Light Water Reactor Fuel

Serpent modelling of pressurized heavy water CANDU reactors

Gustavsson, Cecilia; Andersson, Peter; Branger, Erik; Grape, Sophie et al.

2023

• Ladda ner fulltext (pdf) av Serpent modelling of pressurized heavy water CANDU reactors

Application of Neural Networks to Nuclear Safeguards

Mishra, Vaibhav

2021

• Ladda ner fulltext (pdf) av Application of Neural Networks to Nuclear Safeguards

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"

Mishra, Vaibhav; Elter, Zsolt; Grape, Sophie; Branger, Erik et al.

2020

• Ladda ner fulltext (pdf) av 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"

R&D related to final disposal at Uppsala University: Presentation prepared for the ESARDA Final Disposal WG meeting, Mol Feb 7, 2020

Grape, Sophie; Branger, Erik; Elter, Zsolt; Jansson, Peter et al.

2020

• Ladda ner fulltext (pdf) av R&D related to final disposal at Uppsala University: Presentation prepared for the ESARDA Final Disposal WG meeting, Mol Feb 7, 2020