Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly

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The effect of nuclear data (fission yields, cross sections and emitted spectra) is quantified for spent nuclear fuel assemblies from a realistic boiling water reactor operated over 25 cycles. Nominal calculations are performed with the CASMO5, SIMULATE-3 a ...

This paper preliminarily investigates the use of data-driven surrogates for fuel performance codes. The objective is to develop fast-running models that can be used in the frame of uncertainty quantification and data assimilation studies. In particular, da ...

Noise analysis applied to nuclear reactor physics is a powerful tool to investigate a reactor's kinetic parameters, and more generally underlying physical processes determining core behavior. The kinetic parameters are the coefficients of simplified time-d ...

In the present article, we detail the method used to experimentally determine the power of the CROCUS zero-power reactor, and to subsequently calibrate its ex-core monitor fission chambers. Knowledge of the reactor power is a mandatory quantity for a safe ...

Nuclear reactors are inherently stochastic systems, in which neutronic and thermal-hydraulic parameters fluctuate continuously even during steady-state conditions. In addition, structural components vibrate due to the coolant hydraulic forces. This stochas ...

Detection and direct power conversion of high energy and high intensity ionizing radiation could be a key element in next generation nuclear reactor safety systems and space-born devices. For example, the Fukushima catastrophe in 2011 could have been large ...

Mitochondria are highly dynamics organelles that undergo coordinated cycles of fission and fusion, referred to as mitochondrial dynamics. Mitochondrial dynamics regulate mitochondrial bioenergetics and allow cells to adapt to changing cellular stresses and ...

The safety improvement of nuclear reactors requires continuous efforts in understanding the fundamental physical quantities related to the fission process. In neutronic models, the reactor dynamics is covered by the kinetic parameters to characterize the t ...

New multigroup cross section libraries and associated covariance files that are optimized for the analysis of sodium-cooled fast reactors were generated with the AMPX tools distributed with the SCALE code system. These new libraries account for the fast ne ...

Gamma rays in nuclear reactors, arising either from fission or decay processes, significantly contribute to the heating and dose of the reactor components. Zero power research reactors offer the possibility to measure gamma rays in a purely neutronic envir ...

In the pebble-bed high-temperature reactor under construction in China, called the HTR-PM, the spherical fuel elements continuously flow downward in the cylindrical core. The burnup of each pebble is checked at the core outlet and, according to the achieve ...

The present article gives an overview of the first experimental campaigns carried out in the AKR-2 and CROCUS reactors within the framework of the Horizon 2020 European project CORTEX. CORTEX aims at developing innovative core monitoring techniques that al ...

Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly

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Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics

Artificial Neural Networks as Surrogate Models for Uncertainty Quantification and Data Assimilation in 2-D/3-D Fuel Performance Studies

Experimental and numerical study of stochastic branching noise in nuclear reactors

Power calibration methodology at the CROCUS reactor

Development of Advanced Methodologies for Monitoring and Modelling of Neutron Noise in Modern LWR Cores

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

Crosstalk between Drp1 phosphorylation sites during mitochondrial dynamics and metabolic adaptation

Review of kinetic modulation experiments in low power nuclear reactors

SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX