Zsolt Elter

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

Nuclear safeguards assessments of molten salt reactor spent fuel

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

2024

Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors

Stjärnholm, Sigfrid; Elter, Zsolt; Sjöstrand, Henrik

Ingår i EPJ Web of Conferences, 2024

• DOI för Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors
• Ladda ner fulltext 1 (pdf) av Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors
• Ladda ner fulltext 2 (pdf) av Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors

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

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

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

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

Multi-parameter Optimization of Gamma Emission Tomography Instruments for Irradiated Nuclear Fuel Examination

Senis, Lorenzo; Rathore, Vikram; Andersson Sundén, Erik; Elter, Zsolt et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, 2023

• DOI för Multi-parameter Optimization of Gamma Emission Tomography Instruments for Irradiated Nuclear Fuel Examination
• Ladda ner fulltext (pdf) av Multi-parameter Optimization of Gamma Emission Tomography Instruments for Irradiated Nuclear Fuel Examination

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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A computational methodology for estimating the detected energy spectra of the gamma-ray flux from irradiated nuclear fuel

Senis, Lorenzo; Elter, Zsolt; Rathore, Vikram; Andersson Sundén, Erik et al.

Ingår i IEEE Transactions on Nuclear Science, s. 703-713, 2022

• DOI för A computational methodology for estimating the detected energy spectra of the gamma-ray flux from irradiated nuclear fuel
• Ladda ner fulltext (pdf) av A computational methodology for estimating the detected energy spectra of the gamma-ray flux from irradiated nuclear fuel

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

Evaluation of gamma-ray transmission through rectangular collimator slits for application in nuclear fuel spectrometry

Senis, Lorenzo; Rathore, Vikram; Anastasiadis, Anastasios; Andersson Sundén, Erik et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, 2021

• DOI för Evaluation of gamma-ray transmission through rectangular collimator slits for application in nuclear fuel spectrometry
• Ladda ner fulltext (pdf) av Evaluation of gamma-ray transmission through rectangular collimator slits for application in nuclear fuel spectrometry

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

A methodology to identify partial defects in spent nuclear fuel using gamma spectroscopy data

Elter, Zsolt; Grape, Sophie

Ingår i ESARDA Bulletin, s. 22-31, 2020

• DOI för A methodology to identify partial defects in spent nuclear fuel using gamma spectroscopy data

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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The degradation of gamma-ray mass attenuation of UOX and MOX fuel with nuclear burnup

Atak, Haluk; Anastasiadis, Anastasios; Jansson, Peter; Elter, Zsolt et al.

Ingår i Progress in nuclear energy (New series), 2020

• DOI för The degradation of gamma-ray mass attenuation of UOX and MOX fuel with nuclear burnup
• Ladda ner fulltext (pdf) av The degradation of gamma-ray mass attenuation of UOX and MOX fuel with nuclear burnup

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

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

feign: a Python package to estimate geometric efficiency in passive gamma spectroscopy measurements of nuclear fuel

Elter, Zsolt; Cserkaszky, Aron; Grape, Sophie

Ingår i Journal of Open Source Software, 2019

• DOI för feign: a Python package to estimate geometric efficiency in passive gamma spectroscopy measurements of nuclear fuel
• Ladda ner fulltext (pdf) av feign: a Python package to estimate geometric efficiency in passive gamma spectroscopy measurements of nuclear fuel

Nuclear safeguards assessments of molten salt reactor spent fuel

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

2024

Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors

Stjärnholm, Sigfrid; Elter, Zsolt; Sjöstrand, Henrik

Ingår i EPJ Web of Conferences, 2024

• DOI för Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors
• Ladda ner fulltext 1 (pdf) av Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors
• Ladda ner fulltext 2 (pdf) av Nuclear Data Uncertainty Quantification for Reactor Physics Parameters inFluorine-19-based Molten Salt 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

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

Propagation of F-19 Uncertainties in Molten Salt Reactors

Stjärnholm, Sigfrid; Elter, Zsolt; Sjöstrand, Henrik

2023

• Ladda ner fulltext (pdf) av Propagation of F-19 Uncertainties in Molten Salt Reactors

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

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

Summary Of Recent Investigations Related To Predictions Of The Early Die-away Time τ From The DDSI Instrument

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

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

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

Parametrization of the differential die-away self-interrogation early die-away time for PWR spent fuel assemblies

Caldeira Balkeståhl, Li; Elter, Zsolt; Grape, Sophie

Ingår i ESARDA Bulletin, s. 13-21, 2019

Partial defect identification in PWR spent fuel using Passive Gamma Spectroscopy

Elter, Zsolt; Caldeira Balkeståhl, Li; Grape, Sophie; Hellesen, Carl

2018

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

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