Sophie Grape

Uppsala University — Sweden

Engineering · Physical Sciences

9h-index576citations117works1.22yr avg
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Research Topics

Nuclear reactor physics and engineering(65), Nuclear Physics and Applications(47), Nuclear and radioactivity studies(40), Nuclear Materials and Properties(39), Radiation Detection and Scintillator Technologies(28)

Publications115 total

Development of uranium and plutonium based nuclear weapons—what impacts the choice of fissile material route?
Journal of Strategic Trade Control·2025Open Access
MODENA project: decay heat prediction using non-destructive assay
EPJ Nuclear Sciences & Technologies·2025Open Access
Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept
Annals of Nuclear Energy·2024· 1 citedOpen Access
Prediction of decay heat using non-destructive assay
Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment·2024· 5 citedOpen Access
Prediction of Decay Heat from PWR Spent Nuclear Fuel Using Fuel Parameters
Nuclear Science and Engineering·2024· 1 citedOpen Access
Assessing Pakistan’s Fissile Material Production
Science and Global Security·2024· 3 cited
Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides
Nuclear Technology·2024Open Access
Material attractiveness of irradiated fuel salts from the Seaborg Compact Molten Salt Reactor
Nuclear Engineering and Technology·2024· 3 citedOpen Access
Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor
Nuclear Technology·2024Open Access
Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring
Nuclear Technology·2024Open Access
Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes
Data in Brief·2024· 2 citedOpen Access
Application of Machine Learning to Predict Safeguards Parameters for Irradiated Salts from a Molten Salt Reactor Concept
SSRN Electronic Journal·2024Open Access
Data Library of Irradiated Fuel Salt and Off-Gas Tank Composition for a Molten Salt Reactor Concept Produced with Serpent2 and Sources 4c Codes
SSRN Electronic Journal·2024Open Access
Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes
Data in Brief·2023· 6 citedOpen Access
Plutonium Production under Uranium Constraint
Science and Global Security·2023
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies
Annals of Nuclear Energy·2023· 4 citedOpen Access
Spent Nuclear Fuel Passive Gamma Analysis  And Reproducibility: Application to Skb-50 Assemblies
SSRN Electronic Journal·2023· 1 citedOpen Access
Prediction of Decay Heat from Spent Nuclear Fuel Using Fuel Parameters and Neural Networks
SSRN Electronic Journal·2023Open Access
Statistical analysis of fuel cycle data from Swedish Pressurized Water Reactors and the impact of simplifying assumptions on simulated nuclide inventories
Progress in Nuclear Energy·2022· 2 citedOpen Access
Simulation study of gamma-ray spectroscopy on MYRRHA spent fuel located in lead–bismuth eutectic
Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment·2022· 1 citedOpen Access
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Frequent Co-authors

Peter Jansson(23), Erik Branger(21), Staffan Jacobsson Svärd(17), Anders Sjöland(8), Peter Andersson(6), Zsolt Elter(6), C. Hellesen(5), Matilda Åberg Lindell(5), Anna Davour(5), Vaibhav Mishra(5), Virginie Solans(5), Henrik Sjöstrand(5), Scott Holcombe(4), Holly Trellue(4), Ane Håkansson(4), Sorouche Mirmiran(4), Li Pöder Balkeståhl(3), Stefano Vaccaro(3), Bo Lindberg(3), Stephen J Tobin(3)