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

Partial defect verification of spent VVER fuel using the DCVD

Branger, Erik; Grape, Sophie; Mishra, Vaibhav

Ingår i ESARDA Bulletin, s. 56-61, 2026

• DOI för Partial defect verification of spent VVER fuel using the DCVD
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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
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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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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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Nuclear safeguards assessments of molten salt reactor spent fuel

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

2024

Partial defect verification of spent VVER fuel using the DCVD

Branger, Erik; Grape, Sophie; Mishra, Vaibhav

Ingår i ESARDA Bulletin, s. 56-61, 2026

• DOI för Partial defect verification of spent VVER fuel using the DCVD
• Ladda ner fulltext (pdf) av Partial defect verification of spent VVER fuel using the DCVD

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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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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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
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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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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

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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

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

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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

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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

Studying the effect of load-following operation of the ATOM SMR on radiation emissions from spent nuclear fuel

Olaru, Claudia; Branger, Erik; Ferrero, Vittoria Maria; Grape, Sophie et al.

Comparative Assessment of Spent Fuel Characteristics in BWR Assemblies Using SCALE 6.1 Depletion Simulations

Ray, Nirmal Kumar; Mishra, Vaibhav; Branger, Erik; Grape, Sophie et al.

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