S
Sophie Grape
Researcher at Uppsala University
Publications - 69
Citations - 728
Sophie Grape is an academic researcher from Uppsala University. The author has contributed to research in topics: Spent nuclear fuel & Burnup. The author has an hindex of 9, co-authored 66 publications receiving 666 citations.
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Statistical grounds for determining the ability to detect partial defects using the Digital Cherenkov Viewing Device (DCVD)
TL;DR: The Digital Cherenkov Viewing Device (DCVD) has been used by the IAEA to inspect gross defects in spent fuel as mentioned in this paper, and the DCVD can detect partial defects at the 50% level.
Journal ArticleDOI
Spent Nuclear Fuel Passive Gamma Analysis And Reproducibility: Application to Skb-50 Assemblies
Virginie Solans,Henrik Sjöstrand,P. Hansson,Peter Schillebeeckx,Sophie Grape,E. Branger,Anders Sjöland +6 more
Journal ArticleDOI
Development of a Modeling Approach to Estimate Radiation from a Spent Fuel Rod Quiver
Zs. Elter,Vaibhav Mishra,Sophie Grape,Erik Branger,Peter Jansson,L. Pöder Balkeståhl,M. Hedberg +6 more
TL;DR: A feasibility study related to safeguards verification of quivers, aimed at investigating the gamma and neutron radiation field around a quiver designed by Westinghouse AB and filled with PWR fuel rods irradiated at the Swedish Ringhals site shows that the thick quiver lid attenuates the gamma radiation, thereby making gamma radiation based verification from above the quiver difficult.
Gamma Transport Calculations for Gamma Emission Tomography on Nuclear Fuel within the UGET Project
TL;DR: The unattended gamma emission tomography (UGET) for spent nuclear fuel verification is an on-going project in the IAEA member states' support program as discussed by the authors, and detailed models of the tomographic instruments, including structural materials, and the measured fuel assemblies are used in the simula- tions.
Safeguards Licensing Aspects of a Future Gen IV Test Facility : A Case Study
TL;DR: In this paper, the authors investigated the safeguards licensing aspects of a possible future Gen IV demonstration facility, which was assumed to be located in Sweden, comprising a lead-cooled fast reactor and a reprocessing plant with fuel fabrication.