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M

M.F. Murphy

Researcher at Paul Scherrer Institute

Publications -  36
Citations -  300

M.F. Murphy is an academic researcher from Paul Scherrer Institute. The author has contributed to research in topics: Boiling water reactor & Nuclear reactor core. The author has an hindex of 10, co-authored 36 publications receiving 284 citations.

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Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section libraries

TL;DR: In this article, a detailed three-dimensional continuous energy MCNP4B model of the LWR-PROTEUS critical facility has been developed for the analysis of whole-reactor characteristics using ENDF/B-V, ENDF-B-VI and JEF-2.2 cross-section sets.
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Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel

TL;DR: In this article, high-resolution gamma spectroscopy was performed on individual fuel rods of a fresh, highly heterogeneous Boiling Water Reactor (BWR) fuel assembly, after irradiation at low power in the PROTEUS reactor at PSI, to determine the ratio of neutron captures in 238U (C8) to total fissions (Ftot).
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LWR-PROTEUS verification of reaction rate distributions in modern 10 10 boiling water reactor fuel

TL;DR: In this article, the reaction rate distributions measured with a special gamma-scanning machine employing twin germanium detectors were validated using the experimental results of the LWR-PROTEUS Phase I project corresponding to full-density water moderation conditions (core 1 B).
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Neutronics investigations for the lower part of a westinghouse SVEA-96+ assembly

TL;DR: In this paper, accurate critical experiments have been performed for the validation of total fission (Ftot) and 238U-capture (C8) reaction rate distributions obtained with CASMO-4, HELIOS, BOXER, and MCNP4B for the lower axial region of a real Westinghouse SVEA-96 + fuel assembly.
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Validation of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel

TL;DR: In this paper, a measurement station has been built for the non-destructive investigation of burnt fuel rod segments through high-resolution gamma spectrometry, and four UO2 pressurised water reactor fuel rod segment with different burnup levels between 50 and 100GWd/t and 10 year cooling time have been experimentally characterised using gamma-ray spectrometer to determine 134Cs, 137Cs and 154Eu and their corresponding concentration ratios.