Sophie Grape

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

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

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

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

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

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

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

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

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

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

• 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

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

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

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

Results of the Swedish spent fuel measurement field trials with the Differential Die-Away Self-Interrogation Instrument

Trahan, Alexis C.; McMath, Garrett E.; Mendoza, Paul M.; Trellue, Holly R. et al.

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

• DOI för Results of the Swedish spent fuel measurement field trials with the Differential Die-Away Self-Interrogation Instrument

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

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

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

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

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

Estimating irradiated nuclear fuel characteristics by nonlinear multivariate regression of simulated gamma-ray emissions

Åberg Lindell, Matilda; Andersson, Peter; Grape, Sophie; Håkansson, Ane et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 85-91, 2018

• DOI för Estimating irradiated nuclear fuel characteristics by nonlinear multivariate regression of simulated gamma-ray emissions

The education and training offer in nuclearsafeguards within the EURATOM Research andTraining project “ANNETTE”

Rossa, Riccardo; Niemeyer, Irmgard; Abbas, Kamel; van der Meer, Klaas et al.

2018

Geometry-based Variance Reduction in simulations of Passive Gamma Spectroscopy from Spent Nuclear Fuel

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

2018

MCNP simulations of prototype DDSI detector

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

2018

Application of Multivariate Analysis to Gamma and Neutron Signatures from Spent Nuclear Fuel

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

2018

Partial defect identification in PWR spent fuel using Passive Gamma Spectroscopy

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

2018

Nuclear safeguards verification of modelled BWR fuel using a multivariate analysis approach

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

2018

Nuclear safeguards verification of modelled partial defect PWR fuel using multivariate analysis

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

2018

Improved Cherenkov Light Prediction Model for Enhanced DCVD Performance

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

2018

Discrimination of irradiated MOX fuel from UOX fuel by multivariate statistical analysis of simulated activities of gamma-emitting isotopes

Åberg Lindell, Matilda; Andersson, Peter; Grape, Sophie; Hellesen, Carl et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 67-78, 2018

• DOI för Discrimination of irradiated MOX fuel from UOX fuel by multivariate statistical analysis of simulated activities of gamma-emitting isotopes

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

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

Outcomes of the JNT 1955 Phase I Viability Study of Gamma Emission Tomography for Spent Fuel Verification

Jacobsson, Staffan; Smith, Eric; White, Timothy A.; Mozin, Vladimir et al.

Ingår i ESARDA Bulletin, s. 10-28, 2017

• Ladda ner fulltext (pdf) av Outcomes of the JNT 1955 Phase I Viability Study of Gamma Emission Tomography for Spent Fuel Verification

Outcomes of the JNT 1955 Phase I Viability Study of Gamma EmissionTomography for Spent Fuel Verification

Jacobsson Svärd, Staffan; Smith, Eric; White, Timothy A.; Mozin, Vladimir et al.

2017

Nuclear Spent Fuel Parameter Determination using Multivariate Analysis of Fission Product Gamma Spectra

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

Ingår i Annals of Nuclear Energy, s. 886-895, 2017

• DOI för Nuclear Spent Fuel Parameter Determination using Multivariate Analysis of Fission Product Gamma Spectra

Forskning inom teknisk kärnämneskontroll vid Uppsala universitet under 2014–2015

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

2016

A Viability Study of Gamma Emission Tomography for Spent Fuel Verification: JNT 1955 Phase I Technical Report

Smith, Eric L.; Jacobsson, Staffan; Mozin, Vladimir; Jansson, Peter et al.

Ingår i Geant4 simulation results for the designed UGET-v1 tomographic measurement device., 2016

• Ladda ner fulltext (pdf) av A Viability Study of Gamma Emission Tomography for Spent Fuel Verification: JNT 1955 Phase I Technical Report

Applying image analysis techniques to tomographic images of irradiated nuclear fuel assemblies

Davour, Anna; Jacobsson Svärd, Staffan; Andersson, Peter; Grape, Sophie et al.

Ingår i Annals of Nuclear Energy, s. 223-229, 2016

• DOI för Applying image analysis techniques to tomographic images of irradiated nuclear fuel assemblies

Design of a Prototype Differential Die-Away Instrument proposed for Swedish Spent Nuclear Fuel Characterization

Martinik, Tomas; Henzl, Vladimir; Grape, Sophie; Jansson, Peter et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 55-65, 2016

• DOI för Design of a Prototype Differential Die-Away Instrument proposed for Swedish Spent Nuclear Fuel Characterization

Building a Strategy for ESARDA - Education, Training and Knowledge Management

Grape, Sophie; Persson, Karin; Andersson Sundén, Erik

2015

Students’ Approaches to Learning from Other Students’ Oral Presentations

Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan; Österlund, Michael

2015

Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel

Martinik, Tomas; Grape, Sophie; Jansson, Peter; Henzl, Vlad et al.

2015

• DOI för Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel

Passive Tomography for Spent Fuel Verification: Analysis Framework and Instrument Design Study

White, Timothy A.; Jacobsson Svärd, Staffan; Smith, Eric; Mozin, Vladimir et al.

2015

• DOI för Passive Tomography for Spent Fuel Verification: Analysis Framework and Instrument Design Study

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

Image analysis methods for partial defect detection using tomographic images on nuclear fuel assemblies

Davour, Anna; Jacobsson, Staffan Svärd; Grape, Sophie

2015

Simulation of differential die-away instrument's response to asymmetrically burned spent nuclear fuel

Martinik, Tomas; Vladimir, Henzl; Grape, Sophie; Jacobsson Svärd, Staffan et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 79-85, 2015

• DOI för Simulation of differential die-away instrument's response to asymmetrically burned spent nuclear fuel

A platform for feed-forward and follow-up of students' progression in oral presentation within a study programme

Jansson, Peter; Österlund, Michael; Jacobsson Svärd, Staffan; Grape, Sophie

2015

Basic facts and definitions related to measurement

Grape, Sophie

Ingår i The new nuclear forensics, Oxford University Press, 2015

Gamma spectroscopy as a tool of non-destructive nuclear forensic analysis

Grape, Sophie

Ingår i The new nuclear forensics, Oxford University Press, 2015

Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

Jacobsson Svärd, Staffan; Holcombe, Scott; Grape, Sophie

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 128-141, 2015

• DOI för Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies
• Ladda ner fulltext (pdf) av Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

Gamma-ray Emission Tomography: Modelling and evaluation of partial-defect testing capabilities

Jacobsson Svärd, Staffan; White, Timothy A.; Smith, Eric; Mozin, Vladimir et al.

2014

Experimental and Analytical Plans for the Non-destructive Assay System of the Swedish Encapsulation and Repository Facilities

Tobin, Stephen; Liljenfeldt, Henrik; Trellue, Holly; Grape, Sophie et al.

2014

IPCC förordar kärnkraft för att minska utsläppen

Håkansson, Ane; Ottosson, Jan; Qvist, Staffan; Grape, Sophie et al.

Ingår i Svenska Dagbladet (SvD), 2014

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.

Gamma Transport Calculations for Gamma Emission Tomography on Nuclear Fuel within the UGET Project

Jansson, Peter; Jacobsson Svärd, Staffan; Grape, Sophie; Davour, Anna et al.

2014

Characterization of Spent Nuclear Fuel with a Differential Die-Away Instrument

Martinik, Tomas; Henzl, Vladimir; Grape, Sophie; Jacobsson Svärd, Staffan et al.

2014

Recent modelling studies for analysing the partial-defect detection capability of the Digital Cherenkov Vieweing Device

Grape, Sophie; Jacobsson Svärd, Staffan

Ingår i Esarda Bulletin, s. 3-8, 2014

New perspectives on nuclear power - Generation IV nuclear energy systems to strengthen nuclear non-proliferation and support nuclear disarmament

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

Ingår i Energy Policy, s. 815-819, 2014

• DOI för New perspectives on nuclear power - Generation IV nuclear energy systems to strengthen nuclear non-proliferation and support nuclear disarmament

Partial Defect Evaluation Methodology for Nuclear Safeguards Inspections of Used Nuclear Fuel Using the Digital Cherenkov Viewing Device

Grape, Sophie; Svärd, Staffan Jacobsson; Lindberg, Bo

Ingår i Nuclear Technology, s. 90-98, 2014

• DOI för Partial Defect Evaluation Methodology for Nuclear Safeguards Inspections of Used Nuclear Fuel Using the Digital Cherenkov Viewing Device

Experimental Comparison between High Purity Germanium and Scintillator Detectors for Determining Burnup, Cooling Time and Decay Heat of Used Nuclear Fuel

Jansson, Peter; Grape, Sophie; Tobin, Steve; Liljenfeldt, Henrik

2014

• Ladda ner fulltext (pdf) av Experimental Comparison between High Purity Germanium and Scintillator Detectors for Determining Burnup, Cooling Time and Decay Heat of Used Nuclear Fuel

Students’ approaches to learning from other students’ oral presentations

Grape, Sophie; Jacobsson Svärd, Staffan; Jansson, Peter; Österlund, Michael

2013

• Ladda ner fulltext (pdf) av Students’ approaches to learning from other students’ oral presentations

Assessment of proliferation resistances of aqueous reprocessing techniques using the TOPS methodology

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

Ingår i Annals of Nuclear Energy, s. 390-397, 2013

• DOI för Assessment of proliferation resistances of aqueous reprocessing techniques using the TOPS methodology

Proliferation resistance assessments during the design phase of a fuel recycling facility as a means of reducing proliferation risks

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

2013

A laboratory device for developing analysis tools and methods for gamma emission tomography of nuclear fuel

Jansson, Peter; Grape, Sophie; Jacobsson Svärd, Staffan; Håkansson, Ane

2013

Verifying nuclear fuel assemblies in wet storages on a partial defect level: A software simulation tool for evaluating the capabilities of the Digital Cherenkov Viewing Device

Grape, Sophie; Jacobsson Svärd, Staffan; Lindberg, Bo

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 66-71, 2013

• DOI för Verifying nuclear fuel assemblies in wet storages on a partial defect level: A software simulation tool for evaluating the capabilities of the Digital Cherenkov Viewing Device

Recent modelling studies for analysing the partial-defect detection capability of theDigital Cherenkov Viewing Device

Grape, Sophie; Jacobsson Svärd, Staffan; Lindberg, Bo

2013

Update on the Next Generation Safeguards Initiative’s Spent Fuel Project with Emphasis on Differential Die-Away Research

Martinik, Tomas; Tobin, Stephen; Grape, Sophie; Håkansson, Ane et al.

2013

• Ladda ner fulltext (pdf) av Update on the Next Generation Safeguards Initiative’s Spent Fuel Project with Emphasis on Differential Die-Away Research

Improving the proliferation resistance of generation IV fast reactor fuel cycles using blankets manufactured from spent nuclear fuel.

Hellesen, Carl; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan et al.

2013

Gamma emission tomography of nuclear fuel: Objectives and status of the IAEA UGET project

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

2013

• Ladda ner fulltext (pdf) av Gamma emission tomography of nuclear fuel: Objectives and status of the IAEA UGET project

Update on the Next Generation Safeguards Initiative’s Spent Fuel Nondestructive Assay Project

Tobin, Steve; Grape, Sophie; Jansson, Peter

2013

Prototype Development and Field Trials under the Next Generation Safeguards Initiative Spent Fuel Non-Destructive Assay Project

Tobin, Steve; Grape, Sophie; Jansson, Peter

2013

Improved proliferation resistance of fast reactor blankets manufactured from spent nuclear fuel

Hellesen, Carl; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan et al.

2013

Investigation of Possible Non-Destructive Assay (NDA) Techniques for the Future Swedish Encapsulation Facility

Lundkvist, Niklas; Grape, Sophie; Jansson, Peter; Stephen J., Tobin

2012

The response of lead-tungstate scintillators (PWO) to photons with energies in the range 13 MeV-64 MeV

von Wurtemberg, K. Marcks; Geren, L.; Lundberg, O.; Tegner, P-E et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 36-43, 2012

• DOI för The response of lead-tungstate scintillators (PWO) to photons with energies in the range 13 MeV-64 MeV

Determination of Cerenkov light absorption by fuel pond water using a calibration light source

Parcey, Dennis A.; Chen, J. Dennis; Vogt, Chris; Kosierb, Rick et al.

2011

Partial defect verification using the DCVD: a capability evaluation approach

Grape, Sophie; Jacobsson Svärd, Staffan; Sundkvist, Erik; Parcey, Dennis et al.

2011

Report on the 8th ESARDA course on nuclear safeguards and non-proliferation

Grape, Sophie; Jonter, Thomas

2011

Statistical grounds for determining the ability to detect partial defects using the Digital Cherenkov Viewing Device (DCVD)

Grape, Sophie

2010

• Ladda ner fulltext (pdf) av Statistical grounds for determining the ability to detect partial defects using the Digital Cherenkov Viewing Device (DCVD)

PWO Crystal Measurements and Simulation Studies of Anti-Hyperon Polarisation for PANDA

Grape, Sophie

2008

• Ladda ner fulltext (pdf) av PWO Crystal Measurements and Simulation Studies of Anti-Hyperon Polarisation for PANDA

Hadron physics experiments in antiproton proton reactions with the planned PANDA detector

Calen, Hans; Grape, Sophie; Höistad, Bo; Johansson, Tord et al.

Ingår i Int. J. Mod. Phys. A22, 2007

Test and Developments of Crystals for a High-Resolution Electromagnetic Calorimeter for PANDA

Ohlsson, Sophie

2004

• Ladda ner fulltext (pdf) av Test and Developments of Crystals for a High-Resolution Electromagnetic Calorimeter for PANDA

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

Results of the Swedish spent fuel measurement field trials with the Differential Die-Away Self-Interrogation Instrument

Trahan, Alexis C.; McMath, Garrett E.; Mendoza, Paul M.; Trellue, Holly R. et al.

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

• DOI för Results of the Swedish spent fuel measurement field trials with the Differential Die-Away Self-Interrogation Instrument

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

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

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

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

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

Estimating irradiated nuclear fuel characteristics by nonlinear multivariate regression of simulated gamma-ray emissions

Åberg Lindell, Matilda; Andersson, Peter; Grape, Sophie; Håkansson, Ane et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 85-91, 2018

• DOI för Estimating irradiated nuclear fuel characteristics by nonlinear multivariate regression of simulated gamma-ray emissions

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

Discrimination of irradiated MOX fuel from UOX fuel by multivariate statistical analysis of simulated activities of gamma-emitting isotopes

Åberg Lindell, Matilda; Andersson, Peter; Grape, Sophie; Hellesen, Carl et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 67-78, 2018

• DOI för Discrimination of irradiated MOX fuel from UOX fuel by multivariate statistical analysis of simulated activities of gamma-emitting isotopes

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

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

Outcomes of the JNT 1955 Phase I Viability Study of Gamma Emission Tomography for Spent Fuel Verification

Jacobsson, Staffan; Smith, Eric; White, Timothy A.; Mozin, Vladimir et al.

Ingår i ESARDA Bulletin, s. 10-28, 2017

• Ladda ner fulltext (pdf) av Outcomes of the JNT 1955 Phase I Viability Study of Gamma Emission Tomography for Spent Fuel Verification

Nuclear Spent Fuel Parameter Determination using Multivariate Analysis of Fission Product Gamma Spectra

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

Ingår i Annals of Nuclear Energy, s. 886-895, 2017

• DOI för Nuclear Spent Fuel Parameter Determination using Multivariate Analysis of Fission Product Gamma Spectra

Applying image analysis techniques to tomographic images of irradiated nuclear fuel assemblies

Davour, Anna; Jacobsson Svärd, Staffan; Andersson, Peter; Grape, Sophie et al.

Ingår i Annals of Nuclear Energy, s. 223-229, 2016

• DOI för Applying image analysis techniques to tomographic images of irradiated nuclear fuel assemblies

Design of a Prototype Differential Die-Away Instrument proposed for Swedish Spent Nuclear Fuel Characterization

Martinik, Tomas; Henzl, Vladimir; Grape, Sophie; Jansson, Peter et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 55-65, 2016

• DOI för Design of a Prototype Differential Die-Away Instrument proposed for Swedish Spent Nuclear Fuel Characterization

A Qualitative Analysis of the Neutron Population in Fresh and Spent Fuel Assemblies during Simulated Interrogation using the Differential Die-Away Technique

Lundkvist, Niklas; Goodsell, Alison V.; Grape, Sophie; Hendricks, John S. et al.

Ingår i ESARDA Bulletin, s. 13-21, 2015

Simulation of differential die-away instrument's response to asymmetrically burned spent nuclear fuel

Martinik, Tomas; Vladimir, Henzl; Grape, Sophie; Jacobsson Svärd, Staffan et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 79-85, 2015

• DOI för Simulation of differential die-away instrument's response to asymmetrically burned spent nuclear fuel

Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

Jacobsson Svärd, Staffan; Holcombe, Scott; Grape, Sophie

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 128-141, 2015

• DOI för Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies
• Ladda ner fulltext (pdf) av Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

IPCC förordar kärnkraft för att minska utsläppen

Håkansson, Ane; Ottosson, Jan; Qvist, Staffan; Grape, Sophie et al.

Ingår i Svenska Dagbladet (SvD), 2014

Recent modelling studies for analysing the partial-defect detection capability of the Digital Cherenkov Vieweing Device

Grape, Sophie; Jacobsson Svärd, Staffan

Ingår i Esarda Bulletin, s. 3-8, 2014

New perspectives on nuclear power - Generation IV nuclear energy systems to strengthen nuclear non-proliferation and support nuclear disarmament

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

Ingår i Energy Policy, s. 815-819, 2014

• DOI för New perspectives on nuclear power - Generation IV nuclear energy systems to strengthen nuclear non-proliferation and support nuclear disarmament

Partial Defect Evaluation Methodology for Nuclear Safeguards Inspections of Used Nuclear Fuel Using the Digital Cherenkov Viewing Device

Grape, Sophie; Svärd, Staffan Jacobsson; Lindberg, Bo

Ingår i Nuclear Technology, s. 90-98, 2014

• DOI för Partial Defect Evaluation Methodology for Nuclear Safeguards Inspections of Used Nuclear Fuel Using the Digital Cherenkov Viewing Device

Assessment of proliferation resistances of aqueous reprocessing techniques using the TOPS methodology

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

Ingår i Annals of Nuclear Energy, s. 390-397, 2013

• DOI för Assessment of proliferation resistances of aqueous reprocessing techniques using the TOPS methodology

Verifying nuclear fuel assemblies in wet storages on a partial defect level: A software simulation tool for evaluating the capabilities of the Digital Cherenkov Viewing Device

Grape, Sophie; Jacobsson Svärd, Staffan; Lindberg, Bo

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 66-71, 2013

• DOI för Verifying nuclear fuel assemblies in wet storages on a partial defect level: A software simulation tool for evaluating the capabilities of the Digital Cherenkov Viewing Device

The response of lead-tungstate scintillators (PWO) to photons with energies in the range 13 MeV-64 MeV

von Wurtemberg, K. Marcks; Geren, L.; Lundberg, O.; Tegner, P-E et al.

Ingår i Nuclear Instruments and Methods in Physics Research Section A, s. 36-43, 2012

• DOI för The response of lead-tungstate scintillators (PWO) to photons with energies in the range 13 MeV-64 MeV

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

Basic facts and definitions related to measurement

Grape, Sophie

Ingår i The new nuclear forensics, Oxford University Press, 2015

Gamma spectroscopy as a tool of non-destructive nuclear forensic analysis

Grape, Sophie

Ingår i The new nuclear forensics, Oxford University Press, 2015

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

Education and training at Uppsala University

Grape, Sophie

2024

• Ladda ner fulltext (pdf) av Education and training at Uppsala University

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 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

Applied Nuclear Physics in the Alva Myrdal Centre for Nuclear Disarmament: Non-Proliferation and Safeguards Activities

Grape, Sophie

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

State-of-the-Art Report by WG4: Technical nuclear non-proliferation and safeguards

Grape, Sophie

2022

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

Flipping the physics classroom – First observations

Günter, Katerina; Al-Adili, Ali; Andersson Sundén, Erik; Bissi, Agnese 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

Evaluating Peak Area Uncertainties in Connection to Passive Gamma Measurements of Spent Nuclear Fuel

Solans, Virginie; Sjöstrand, Henrik; Jansson, Peter; Grape, Sophie et al.

Ingår i Proceedings, 2021

• DOI för Evaluating Peak Area Uncertainties in Connection to Passive Gamma Measurements of Spent Nuclear Fuel
• Ladda ner fulltext (pdf) av Evaluating Peak Area Uncertainties in Connection to Passive Gamma Measurements of Spent Nuclear Fuel

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

I could rewind and understand and google – Insights into a mixed-methods study on flipped classrooms in higher physics education

Günter, Katerina Pia; Tarrío, Diego; Chiodaroli, Marco; Freyhult, Lisa et al.

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

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

The education and training offer in nuclearsafeguards within the EURATOM Research andTraining project “ANNETTE”

Rossa, Riccardo; Niemeyer, Irmgard; Abbas, Kamel; van der Meer, Klaas et al.

2018

Geometry-based Variance Reduction in simulations of Passive Gamma Spectroscopy from Spent Nuclear Fuel

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

2018

MCNP simulations of prototype DDSI detector

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

2018

Application of Multivariate Analysis to Gamma and Neutron Signatures from Spent Nuclear Fuel

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

2018

Partial defect identification in PWR spent fuel using Passive Gamma Spectroscopy

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

2018

Nuclear safeguards verification of modelled BWR fuel using a multivariate analysis approach

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

2018

Nuclear safeguards verification of modelled partial defect PWR fuel using multivariate analysis

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

2018

Improved Cherenkov Light Prediction Model for Enhanced DCVD Performance

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

2018

Outcomes of the JNT 1955 Phase I Viability Study of Gamma EmissionTomography for Spent Fuel Verification

Jacobsson Svärd, Staffan; Smith, Eric; White, Timothy A.; Mozin, Vladimir et al.

2017

Tomographic determination of spent fuel assembly pin-wise burnup and cooling time for detection of anomalies

Jacobsson Svärd, Staffan; Andersson, Peter; Davour, Anna; Grape, Sophie et al.

2015

• DOI för Tomographic determination of spent fuel assembly pin-wise burnup and cooling time for detection of anomalies

Building a Strategy for ESARDA - Education, Training and Knowledge Management

Grape, Sophie; Persson, Karin; Andersson Sundén, Erik

2015

Students’ Approaches to Learning from Other Students’ Oral Presentations

Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan; Österlund, Michael

2015

Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel

Martinik, Tomas; Grape, Sophie; Jansson, Peter; Henzl, Vlad et al.

2015

• DOI för Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel

Passive Tomography for Spent Fuel Verification: Analysis Framework and Instrument Design Study

White, Timothy A.; Jacobsson Svärd, Staffan; Smith, Eric; Mozin, Vladimir et al.

2015

• DOI för Passive Tomography for Spent Fuel Verification: Analysis Framework and Instrument Design Study

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

Image analysis methods for partial defect detection using tomographic images on nuclear fuel assemblies

Davour, Anna; Jacobsson, Staffan Svärd; Grape, Sophie

2015

A platform for feed-forward and follow-up of students' progression in oral presentation within a study programme

Jansson, Peter; Österlund, Michael; Jacobsson Svärd, Staffan; Grape, Sophie

2015

Improved DCVD assessments of irradiated nuclear fuel using image analysis techniques

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

2014

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

Gamma-ray Emission Tomography: Modelling and evaluation of partial-defect testing capabilities

Jacobsson Svärd, Staffan; White, Timothy A.; Smith, Eric; Mozin, Vladimir et al.

2014

Experimental and Analytical Plans for the Non-destructive Assay System of the Swedish Encapsulation and Repository Facilities

Tobin, Stephen; Liljenfeldt, Henrik; Trellue, Holly; Grape, Sophie et al.

2014

Gamma Transport Calculations for Gamma Emission Tomography on Nuclear Fuel within the UGET Project

Jansson, Peter; Jacobsson Svärd, Staffan; Grape, Sophie; Davour, Anna et al.

2014

Characterization of Spent Nuclear Fuel with a Differential Die-Away Instrument

Martinik, Tomas; Henzl, Vladimir; Grape, Sophie; Jacobsson Svärd, Staffan et al.

2014

Experimental Comparison between High Purity Germanium and Scintillator Detectors for Determining Burnup, Cooling Time and Decay Heat of Used Nuclear Fuel

Jansson, Peter; Grape, Sophie; Tobin, Steve; Liljenfeldt, Henrik

2014

• Ladda ner fulltext (pdf) av Experimental Comparison between High Purity Germanium and Scintillator Detectors for Determining Burnup, Cooling Time and Decay Heat of Used Nuclear Fuel

Students’ approaches to learning from other students’ oral presentations

Grape, Sophie; Jacobsson Svärd, Staffan; Jansson, Peter; Österlund, Michael

2013

• Ladda ner fulltext (pdf) av Students’ approaches to learning from other students’ oral presentations

Schematic design and safeguards instrumentation of a Gen IV fuel recycling facility.

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

2013

Proliferation resistance assessments during the design phase of a fuel recycling facility as a means of reducing proliferation risks

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

2013

A laboratory device for developing analysis tools and methods for gamma emission tomography of nuclear fuel

Jansson, Peter; Grape, Sophie; Jacobsson Svärd, Staffan; Håkansson, Ane

2013

Recent modelling studies for analysing the partial-defect detection capability of theDigital Cherenkov Viewing Device

Grape, Sophie; Jacobsson Svärd, Staffan; Lindberg, Bo

2013

Update on the Next Generation Safeguards Initiative’s Spent Fuel Project with Emphasis on Differential Die-Away Research

Martinik, Tomas; Tobin, Stephen; Grape, Sophie; Håkansson, Ane et al.

2013

• Ladda ner fulltext (pdf) av Update on the Next Generation Safeguards Initiative’s Spent Fuel Project with Emphasis on Differential Die-Away Research

Improving the proliferation resistance of generation IV fast reactor fuel cycles using blankets manufactured from spent nuclear fuel.

Hellesen, Carl; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan et al.

2013

Gamma emission tomography of nuclear fuel: Objectives and status of the IAEA UGET project

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

2013

• Ladda ner fulltext (pdf) av Gamma emission tomography of nuclear fuel: Objectives and status of the IAEA UGET project

Update on the Next Generation Safeguards Initiative’s Spent Fuel Nondestructive Assay Project

Tobin, Steve; Grape, Sophie; Jansson, Peter

2013

Prototype Development and Field Trials under the Next Generation Safeguards Initiative Spent Fuel Non-Destructive Assay Project

Tobin, Steve; Grape, Sophie; Jansson, Peter

2013

Improved proliferation resistance of fast reactor blankets manufactured from spent nuclear fuel

Hellesen, Carl; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan et al.

2013

Investigation of Possible Non-Destructive Assay (NDA) Techniques for the Future Swedish Encapsulation Facility

Lundkvist, Niklas; Grape, Sophie; Jansson, Peter; Stephen J., Tobin

2012

Determination of Cerenkov light absorption by fuel pond water using a calibration light source

Parcey, Dennis A.; Chen, J. Dennis; Vogt, Chris; Kosierb, Rick et al.

2011

Partial defect verification using the DCVD: a capability evaluation approach

Grape, Sophie; Jacobsson Svärd, Staffan; Sundkvist, Erik; Parcey, Dennis et al.

2011

Report on the 8th ESARDA course on nuclear safeguards and non-proliferation

Grape, Sophie; Jonter, Thomas

2011

Modelling Cherenkov light from irradiated nuclear fuel assemblies using GEANT4

Grape, Sophie; Jacobsson Svärd, Staffan; Lindberg, Bo; Hjalmarsson, Anders

2010

Modeling of the Cherenkov Light Emission from Nuclear Fuel Assemblies with Partial Defects

Jacobsson Svärd, Staffan; Grape, Sophie; Hjalmarsson, Anders

Ingår i PHYSOR 2010, 2010

Safeguards Licensing Aspects of a Future Gen IV Test Facility: A Case Study

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

2010

Physics with the PANDA detector at FAIR

Calen, Hans; Grape, Sophie; Höistad, Bo; Johansson, Tord et al.

Ingår i Nucl. Phys. A790, 2007

Using anti-protons to measure nucleon structure: Prospects at PANDA

Calen, Hans; Grape, Sophie; Höistad, Bo; Johansson, Tord et al.

Ingår i 15th International Workshop on Deep-Inelastic Scattering and Related Subjects (DIS2007), Munich, Germany, 2007

Hadron physics experiments in antiproton proton reactions with the planned PANDA detector

Calen, Hans; Grape, Sophie; Höistad, Bo; Johansson, Tord et al.

Ingår i Int. J. Mod. Phys. A22, 2007

PWO Crystal Measurements and Simulation Studies of Anti-Hyperon Polarisation for PANDA

Grape, Sophie

2008

• Ladda ner fulltext (pdf) av PWO Crystal Measurements and Simulation Studies of Anti-Hyperon Polarisation for PANDA

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

A Viability Study of Gamma Emission Tomography for Spent Fuel Verification: JNT 1955 Phase I Technical Report

Smith, Eric L.; Jacobsson, Staffan; Mozin, Vladimir; Jansson, Peter et al.

Ingår i Geant4 simulation results for the designed UGET-v1 tomographic measurement device., 2016

• Ladda ner fulltext (pdf) av A Viability Study of Gamma Emission Tomography for Spent Fuel Verification: JNT 1955 Phase I Technical Report

Svensk elförsörjning i framtiden – en fråga med globala dimensioner: En tvärvetenskaplig rapport från Uppsala universitet

Håkansson, Ane; Davour, Anna; Grape, Sophie; Hellesen, Carl et al.

2014

• Ladda ner fulltext (pdf) av Svensk elförsörjning i framtiden – en fråga med globala dimensioner: En tvärvetenskaplig rapport från Uppsala universitet

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.

Statistical grounds for determining the ability to detect partial defects using the Digital Cherenkov Viewing Device (DCVD)

Grape, Sophie

2010

• Ladda ner fulltext (pdf) av Statistical grounds for determining the ability to detect partial defects using the Digital Cherenkov Viewing Device (DCVD)

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

Spent fuel characterization research at Uppsala University: Presented at kick-off meeting for IAEA CRP on spent fuel characterisation, 2021-02-16

Jansson, Peter; Andersson, Peter; Grape, Sophie; Sjöstrand, Henrik

2021

• Ladda ner fulltext 1 (pdf) av Spent fuel characterization research at Uppsala University: Presented at kick-off meeting for IAEA CRP on spent fuel characterisation, 2021-02-16
• Ladda ner fulltext 2 (zip) av Spent fuel characterization research at Uppsala University: Presented at kick-off meeting for IAEA CRP on spent fuel characterisation, 2021-02-16

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