Sophie Grape

Associate Professor

Uppsala University

Sweden

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Research Interests

Nuclear Physics

100%

Materials Chemistry

20%

Radiochemistry

100%

Neutron Science

100%

Nuclear Engineering

90%

Reactor Physics

70%

Radiation Physics

40%

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Articles21

Prediction of decay heat using non-destructive assay

Year:

2025

Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept

Year:

2025

Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Year:

2024

Data library of irradiated fuel salt and off-gas tank composition for a molten salt reactor concept produced with Serpent2 and SOURCES 4C codes

Year:

2024

Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes

Year:

2024

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

Year:

2024

Assessing Pakistan’s Fissile Material Production

Year:

2024

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

Year:

2023

Statistical analysis of fuel cycle data from Swedish Pressurized Water Reactors and the impact of simplifying assumptions on simulated nuclide inventories

Year:

2023

Simulating submarine reactor fuel in light of the AUKUS deal

Year:

2023

Plutonium Production under Uranium Constraint

Year:

2023

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

Year:

2022

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

Year:

2022

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

Year:

2021

DEVELOPMENT OF A MODELING APPROACH TO ESTIMATE RADIATION FROM A SPENT FUEL ROD QUIVER

Year:

2021

Estimating gamma and neutron radiation fluxes around BWR quivers for nuclear safeguards verification purposes

Year:

2020

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

Year:

2020

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

Year:

2020

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

Year:

2020

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

Year:

2020

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

Year:

2020

Collaborators3

Henrik Sjöstrand

Uppsala University

SWEDEN

Cecilia Gustavsson

Associate professor

Uppsala University

SWEDEN

Vaibhav Mishra

Uppsala University

SWEDEN

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