Erik Branger

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

Retrieving information about the Ågesta reactor in Sweden

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia

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

Image analysis to support DCVD verification

Branger, Erik; Grape, Sophie; Preston, Markus

Ingår i Proceedings of the INMM & ESARDA Joint Annual Meeting, May 22-26, 2023, 2023

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

MODENA project: decay heat prediction using non-destructive assay

Solans, Virginie; Branger, Erik; Grape, Sophie; Sjöstrand, Henrik

Ingår i EPJ Nuclear sciences & technologies, 2025

• DOI för MODENA project: decay heat prediction using non-destructive assay
• Ladda ner fulltext (pdf) av MODENA project: decay heat prediction using non-destructive assay

Development of uranium and plutonium based nuclear weapons—what impacts the choice of fissile material route?

, Sophie; , Erik; , Vitaly; , Cecilia et al.

Ingår i Journal of Strategic Trade Control, 2025

• DOI för Development of uranium and plutonium based nuclear weapons—what impacts the choice of fissile material route?

Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor

Trombetta, Débora M.; Branger, Erik; Preston, Markus; Grape, Sophie

Ingår i Nuclear Technology, s. 344-357, 2025

• DOI för Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor
• Ladda ner fulltext (pdf) av Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor

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

MODENA project: decay heat prediction using non-destructive assay

Solans, Virginie; Branger, Erik; Grape, Sophie; Sjöstrand, Henrik

Ingår i EPJ Nuclear sciences & technologies, 2025

• DOI för MODENA project: decay heat prediction using non-destructive assay
• Ladda ner fulltext (pdf) av MODENA project: decay heat prediction using non-destructive assay

Development of uranium and plutonium based nuclear weapons—what impacts the choice of fissile material route?

, Sophie; , Erik; , Vitaly; , Cecilia et al.

Ingår i Journal of Strategic Trade Control, 2025

• DOI för Development of uranium and plutonium based nuclear weapons—what impacts the choice of fissile material route?

Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor

Trombetta, Débora M.; Branger, Erik; Preston, Markus; Grape, Sophie

Ingår i Nuclear Technology, s. 344-357, 2025

• DOI för Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor
• Ladda ner fulltext (pdf) av Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor

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

Prediction of decay heat using non-destructive assays

Solans, Virginie; Sjöstrand, Henrik; Grape, Sophie; Branger, Erik et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, 2025

• DOI för Prediction of decay heat using non-destructive assays
• Ladda ner fulltext (pdf) av Prediction of decay heat using non-destructive assays

Prediction of Decay Heat from PWR Spent Nuclear Fuel Using Fuel Parameters

Solans, Virginie; Sjöstrand, Henrik; Grape, Sophie; Branger, Erik et al.

Ingår i Nuclear science and engineering, s. 930-940, 2024

• DOI för Prediction of Decay Heat from PWR Spent Nuclear Fuel Using Fuel Parameters
• Ladda ner fulltext (pdf) av Prediction of Decay Heat from PWR Spent Nuclear Fuel Using Fuel Parameters

Assessing Pakistan's Fissile Material Production

Schalz, Max; Branger, Erik; Göttsche, Malte; Grape, Sophie et al.

Ingår i Science and Global Security, s. 42-67, 2024

• DOI för Assessing Pakistan's Fissile Material Production

Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring

Preston, Markus; Branger, Erik; Grape, Sophie; Khotiaintseva, Olena

Ingår i Nuclear Technology, s. 1952-1974, 2024

• DOI för Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring
• Ladda ner fulltext (pdf) av Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring

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
• Ladda ner fulltext (pdf) av Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor

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
• Ladda ner fulltext (pdf) av Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes

Simulating submarine reactor fuel in light of the AUKUS deal

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia; Kelley, Robert et al.

Ingår i ESARDA Bulletin - The International Journal of Nuclear Safeguards and Non-proliferation, s. 34-43, 2023

• DOI för Simulating submarine reactor fuel in light of the AUKUS deal
• Ladda ner fulltext (pdf) av Simulating submarine reactor fuel in light of the AUKUS deal

Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies

Solans, Virginie; Sjöstrand, Henrik; Jansson, Peter; Schillebeeckx, Peter et al.

Ingår i Annals of Nuclear Energy, 2023

• DOI för Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies
• Ladda ner fulltext (pdf) av Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies

Plutonium Production under Uranium Constraint

Branger, Erik; Andersson, Peter; Fedchenko, Vitaly; Grape, Sophie et al.

Ingår i Science and Global Security, s. 115-136, 2023

• DOI för Plutonium Production under Uranium Constraint

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
• Ladda ner fulltext (pdf) av Statistical analysis of fuel cycle data from Swedish Pressurized Water Reactors and the impact of simplifying assumptions on simulated nuclide inventories

Simulation study of gamma-ray spectroscopy on MYRRHA spent fuel located in lead–bismuth eutectic

Preston, Markus; Borella, Alessandro; Branger, Erik; Grape, Sophie et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, 2022

• DOI för Simulation study of gamma-ray spectroscopy on MYRRHA spent fuel located in lead–bismuth eutectic
• Ladda ner fulltext (pdf) av Simulation study of gamma-ray spectroscopy on MYRRHA spent fuel located in lead–bismuth eutectic

Studies of the impact of beta contributions on Cherenkov light emission by spent nuclear fuel

Branger, Erik; Elter, Zsolt; Grape, Sophie; Preston, Markus

Ingår i ESARDA Bulletin, s. 2-9, 2022

• DOI för Studies of the impact of beta contributions on Cherenkov light emission by spent nuclear fuel

Analysis of radiation emission from MYRRHA spent fuel and implications for non-destructive safeguards verification

Preston, Markus; Borella, Alessandro; Branger, Erik; Grape, Sophie et al.

Ingår i Annals of Nuclear Energy, s. 108525, 2021

• DOI för Analysis of radiation emission from MYRRHA spent fuel and implications for non-destructive safeguards verification

Sensitivity analysis of the Rossi-Alpha Distribution and the early die-away time τ from the DDSI instrument due to modelling assumptions

Grape, Sophie; Elter, Zsolt; Branger, Erik

Ingår i The ESARDA Bulletin, 2021

Investigating the sensitivity to irradiation history when predicting fuel parameters using random forest regression

Branger, Erik; Elter, Zsolt; Grape, Sophie; Preston, Markus

Ingår i ESARDA Bulletin, s. 2-10, 2021

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
• Ladda ner fulltext (pdf) av Estimating gamma and neutron radiation fluxes around BWR quivers for nuclear safeguards verification purposes

Partial defect detection using the DCVD and a segmented Region-Of-Interest

Branger, Erik; Grape, Sophie; Jansson, Peter

Ingår i Journal of Instrumentation, 2020

• DOI för Partial defect detection using the DCVD and a segmented Region-Of-Interest
• Ladda ner fulltext (pdf) av Partial defect detection using the DCVD and a segmented Region-Of-Interest

Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code

Elter, Zsolt; Pöder Balkeståhl, Li; Branger, Erik; Grape, Sophie

Ingår i Data in Brief, 2020

• DOI för Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code
• Ladda ner fulltext (pdf) av Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code

Time stamped list mode data from gamma-ray spectroscopic measurements on 47 nuclear fuel assemblies performed at Clab, Sweden, September 2016 through March 2019

Jansson, Peter; Bengtsson, Martin; Bäckström, Ulrika; Grape, Sophie et al.

Ingår i Data in Brief, 2020

• DOI för Time stamped list mode data from gamma-ray spectroscopic measurements on 47 nuclear fuel assemblies performed at Clab, Sweden, September 2016 through March 2019
• Ladda ner fulltext (pdf) av Time stamped list mode data from gamma-ray spectroscopic measurements on 47 nuclear fuel assemblies performed at Clab, Sweden, September 2016 through March 2019

Determination of spent nuclear fuel parameters using modelled signatures from non-destructive assay and Random Forest regression

Grape, Sophie; Branger, Erik; Elter, Zsolt; Pöder Balkeståhl, Li

Ingår i Nuclear Instruments and Methods in Physics Research Section A, 2020

• DOI för Determination of spent nuclear fuel parameters using modelled signatures from non-destructive assay and Random Forest regression
• Ladda ner fulltext (pdf) av Determination of spent nuclear fuel parameters using modelled signatures from non-destructive assay and Random Forest regression

On the inclusion of light transport in prediction tools for Cherenkov light intensity assessment of irradiated nuclear fuel assemblies

Branger, Erik; Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan

Ingår i Journal of Instrumentation, 2019

• DOI för On the inclusion of light transport in prediction tools for Cherenkov light intensity assessment of irradiated nuclear fuel assemblies
• Ladda ner fulltext (pdf) av On the inclusion of light transport in prediction tools for Cherenkov light intensity assessment of irradiated nuclear fuel assemblies

Verifying PWR assemblies with rod cluster control assembly inserts using a DCVD

Branger, Erik; Grape, Sophie; Jansson, Peter

Ingår i ESARDA Bulletin, s. 35-40, 2019

Experimental evaluation of models for predicting Cherenkov light intensities from short-cooled nuclear fuel assemblies

Branger, Erik; Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan

Ingår i Journal of Instrumentation, 2018

• DOI för Experimental evaluation of models for predicting Cherenkov light intensities from short-cooled nuclear fuel assemblies
• Ladda ner fulltext (pdf) av Experimental evaluation of models for predicting Cherenkov light intensities from short-cooled nuclear fuel assemblies

Experimental study of background subtraction in Digital Cherenkov Viewing Device measurements

Branger, Erik; Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan

Ingår i Journal of Instrumentation, 2018

• DOI för Experimental study of background subtraction in Digital Cherenkov Viewing Device measurements
• Ladda ner fulltext (pdf) av Experimental study of background subtraction in Digital Cherenkov Viewing Device measurements

Investigating the Cherenkov light production due to cross-talk in closely stored nuclear fuel assemblies in wet storage

Branger, Erik; Grape, Sophie; Jansson, Peter; Andersson Sundén, Erik et al.

Ingår i ESARDA Bulletin, s. 66-74, 2018

• DOI för Investigating the Cherenkov light production due to cross-talk in closely stored nuclear fuel assemblies in wet storage

Comparison of prediction models for Cherenkov light emissions from nuclear fuel assemblies

Branger, Erik; Grape, Sophie; Jacobsson, Staffan; Jansson, Peter et al.

Ingår i Journal of Instrumentation, 2017

• DOI för Comparison of prediction models for Cherenkov light emissions from nuclear fuel assemblies
• Ladda ner fulltext (pdf) av Comparison of prediction models for Cherenkov light emissions from nuclear fuel assemblies

On Cherenkov light production by irradiated nuclear fuel rods

Branger, Erik; Grape, Sophie; Jacobsson, Staffan; Jansson, Peter et al.

Ingår i Journal of Instrumentation, 2017

• DOI för On Cherenkov light production by irradiated nuclear fuel rods
• Ladda ner fulltext (pdf) av On Cherenkov light production by irradiated nuclear fuel rods

Time stamped list mode data from gamma-ray spectroscopic measurements on 47 nuclear fuel assemblies performed at Clab, Sweden, September 2016 through March 2019

Jansson, Peter; Bengtsson, Martin; Bäckström, Ulrika; Grape, Sophie et al.

2020

Enhancing the performance of the Digital Cherenkov Viewing Device: Detecting partial defects in irradiated nuclear fuel assemblies using Cherenkov light

Branger, Erik

2018

• Ladda ner fulltext (pdf) av Enhancing the performance of the Digital Cherenkov Viewing Device: Detecting partial defects in irradiated nuclear fuel assemblies using Cherenkov light

Nuclear safeguards assessments of molten salt reactor spent fuel

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

2024

Predicting Decay Heat By Combining Fuel Parameters With Gamma And Neutron Data Using Machine Learning

Solans, Virginie; Sjöstrand, Henrik; Grape, Sophie; Branger, Erik et al.

2024

Researching nuclear reactors deployed at sea from a 3S perspective

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

2024

Integration of Small Modular Reactors in the Swedish Nuclear Energy System: A Proliferation Resistance Study

Olaru, Claudia; Branger, Erik; Grape, Sophie

2024

Assessment of a liquid organic scintillation detector for fast neutron measurements in the context of verification of nuclear weapon dismantlement

Trombetta, Débora; Göök, Alf; Branger, Erik; Andersson, Peter et al.

2024

Exploring methods to reconstruct historic reactor operation

Gustavsson, Cecilia; Andersson, Peter; Branger, Erik; Grape, Sophie

Ingår i Alva Myrdal Centre AMC Annual conference 2024, 18-19 June, 2024., 2024

Modelling fissile production in the Experimental Light Water Reactor (ELWR) of DPRK

Gustavsson, Cecilia; Andersson, Peter; Branger, Erik; Chrisopher, Grant et al.

Ingår i Alva Myrdal Centre AMC Annual conference 2024, 18-19 June, 2024, 2024

Exploring reasons behind the development of uranium and plutonium based nuclear weapons in states

Grape, Sophie; Branger, Erik; Kelley, Robert; Fedchenko, Vitaly

2024

IPNDV disarmament verification exercise: in perspective of AMC WG4 participation

Trombetta, Débora; Branger, Erik; Göök, Alf; Grape, Sophie et al.

2023

Investigating material attractiveness of minor actinides fuel for waste transmutation

Trombetta, Débora M.; Branger, Erik; Preston, Markus; Grape, Sophie

Ingår i Proceedings of the INMM & ESARDA Joint Annual Meeting, May 22-26, 2023, 2023

Decay heat predictions using gamma spectroscopy and neutron coincidence data

Solans, Virginie; Sjöstrand, Henrik; Grape, Sophie; Branger, Erik et al.

2023

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

Possibilities for monitoring the composition of an iPWR core using ex-core neutron detectors

Preston, Markus; Branger, Erik; Grape, Sophie; Khotiaintseva, Olena et al.

Ingår i Proceedings of the INMM & ESARDA Joint Annual Meeting, 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

Experimental verification of simulated predictions from the DDSI instrument

Grape, Sophie; Branger, Erik; Elter, Zsolt

Ingår i Proceedings of the INMM & ESARDA Joint Annual Meeting, May 22-26, 2023, s. 1-10, 2023

Retrieving information about the Ågesta reactor in Sweden

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia

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

Image analysis to support DCVD verification

Branger, Erik; Grape, Sophie; Preston, Markus

Ingår i Proceedings of the INMM & ESARDA Joint Annual Meeting, May 22-26, 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

Rossi-Alpha Distribution Analysis of DDSI Data For Spent Nuclear Fuel Investigation

Solans, Virginie; Grape, Sophie; Sjöstrand, Henrik; Branger, Erik et al.

2022

• Ladda ner fulltext (pdf) av Rossi-Alpha Distribution Analysis of DDSI Data For Spent Nuclear Fuel Investigation

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

Overview of initial work on spent-fuel verification at MYRRHA

Preston, Markus; Borella, Alessandro; Rossa, Riccardo; Branger, Erik et al.

Ingår i Symposium on International Safeguards, 2022

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

• Ladda ner fulltext (pdf) av Research on safeguarding molten salt reactor systems at Uppsala University

Effects of modelling assumptions on Cherenkov light intensity predictions

Branger, Erik; Grape, Sophie; Preston, Markus

2022

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

• Ladda ner fulltext (pdf) av Coincidence spectroscopy for increased sensitivity in radionuclide monitoring

Development of a PhD course in verification of nuclear test explosions under AMC

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia; Österlund, Michael et al.

2022

• Ladda ner fulltext (pdf) av Development of a PhD course in verification of nuclear test explosions under AMC

Studies of naval reactor core properties in light of recent AUKUS developments

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia; Kelley, Robert. E. et al.

2022

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

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

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

2021

SUMMARY OF RECENT INVESTIGATIONS RELATED TO PREDICTIONS OF THE EARLY DIE-AWAY TIME τ FROM THE DDSI INSTRUMENT

Grape, Sophie; Elter, Zsolt; Branger, Erik

Ingår i Proceedings of the INMM & ESARDA Joint Virtual Annual MeetingAugust 23-26 & August 30-September 1, 2021, 2021

Combining DCVD measurements at different alignments for enhanced partial defect detection performance

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

Ingår i Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting August 23-26 & August 30-September 1, 2021, 2021

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

Enhanced verification of irradiated nuclear fuel using Cherenkov light

Branger, Erik

2019

Improved Cherenkov Light Prediction Model for Enhanced DCVD Performance

Branger, Erik; Grape, Sophie; Jansson, Peter; Jacobsson, Staffan

2018

Improving the prediction model for Cherenkov light generation by irradiated nuclear fuel assemblies in wet storage for enhanced partial-defect verification capability

Branger, Erik; Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan

s. 22-29, 2015

• DOI för Improving the prediction model for Cherenkov light generation by irradiated nuclear fuel assemblies in wet storage for enhanced partial-defect verification capability

Towards unattended partial-defect verification of irradiated nuclear fuel assemblies using the DCVD

Branger, Erik; Jacobsson Svärd, Staffan; Grape, Sophie; Wernersson, Erik L. G.

2014

Improved DCVD assessments of irradiated nuclear fuel using image analysis techniques

Branger, Erik; Grape, Sophie; Jacobsson Svärd, Staffan; Wernersson, Erik L. G.

2014

Studies of Cherenkov light production in irradiated nuclear fuel assemblies

Branger, Erik

2016

• Ladda ner fulltext (pdf) av Studies of Cherenkov light production in irradiated nuclear fuel assemblies

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

State-of-the-Art Report: Prepared by Working Group 4: Technical nuclear non-proliferation and safeguards under the Alva Myrdal Centre for nuclear disarmament

Grape, Sophie; Andersson, Peter; Branger, Erik; Fedchenko, Vitaly et al.

2022

• Ladda ner fulltext (pdf) av State-of-the-Art Report: Prepared by Working Group 4: Technical nuclear non-proliferation and safeguards under the Alva Myrdal Centre for nuclear disarmament

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"

Research within technical safeguard at Uppsala university during 2016-2018

Grape, Sophie; Branger, Erik; Caldeira Balkeståhl, Li; Elter, Zsolt et al.

2019

Forskning inom teknisk kärnämneskontroll vid Uppsala universitet under 2014–2015

Grape, Sophie; Jacobsson Svärd, Staffan; Jansson, Peter; Hellesen, Carl et al.

2016

Image analysis as a tool for improved use of the Digital Cherenkov Viewing Device for inspection of irradiated PWR fuel assemblies.

Branger, Erik; Wernersson, Erik L. G.; Grape, Sophie; Jacobsson, Staffan Svärd

2014

• Ladda ner fulltext (pdf) av Image analysis as a tool for improved use of the Digital Cherenkov Viewing Device for inspection of irradiated PWR fuel assemblies.

Status of spent fuel characterization research at Uppsala University: Presented at IAEA CRP meeting on SNF characterisation 2021-06-28

Jansson, Peter; Sjöstrand, Henrik; Grape, Sophie; Andersson, Peter et al.

2021

• DOI för Status of spent fuel characterization research at Uppsala University: Presented at IAEA CRP meeting on SNF characterisation 2021-06-28

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