Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel

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In response to the need for validating high-fidelity deterministic neutronics solvers capable of providing pin-resolved neutron flux distributions, intra-pin reaction rates measurements were performed in the CROCUS experimental reactor. A specially designe ...

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We experimentally demonstrate the advantages of gamma detection for noise measurements to deter-mine the prompt neutron decay constant a of a nuclear reactor using the power spectral density (PSD) method, coupled to a new uncertainty estimation scheme base ...

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The present doctoral work was performed to contribute to the conceptual design development and safety assessment of a Generation IV Sodium Fast Reactor (SFR) in the frame of the European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ES ...

Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel

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Intra-pin Reaction Rate Measurements in the CROCUS Experimental Reactor

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Design and operational guidelines of solar-driven catalytic conversion of CO2 and H2 to fuels

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Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments

Gamma-Blind Fast Neutron Detection for Spent Nuclear Fuel Characterization

Down-conversion of a single photon as a probe of many-body localization

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Data-Driven Predictive Models: Calculational Bias in Characterization of Spent Nuclear Fuel

Miniature and Minimalistic Neutron Detectors for Online High-Resolution Experiments in the Zero-Power Reactor CROCUS

On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM (R): state of the art, lessons learned and perspectives

Advanced methodologies for modeling and assessment of SFR safety functions