Advancing Multi-Dimensional Simulation of Nuclear Fuel Behavior: from LOCA Analysis to Fast Reactor Applications

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The problem of avoiding saturation of the coil currents is critical in large tokamaks with superconducting coils like ITER. Indeed, if the current limits are reached, a loss of control of the plasma may lead to a major disruption. Therefore, a current limi ...

Zirconium-based cladding tubes, mainly used as fuel cladding materials in light water reactors, serve as the primary barrier insulating the radioactive fission products from the environment. During operation, the cladding interacts with the coolant water, ...

The systematic use of high-fidelity high-resolution codes which allow the prediction of safety parameters on a local scale, can result in more efficient use of the nuclear fuel and of the nuclear reactor.The Laboratory of Reactor Physics and Thermal-Hydrau ...

Gamma-ray spectroscopy is an effective technique for radioactive material characterization, routine inventory verification, nuclear safeguards, health physics, and source search scenarios. Gamma-ray spectrometers typically cannot be operated in the immedia ...

Nuclear fusion, with its potential to provide a nearly unlimited energy source, has inspired scientists to work on the development of fusion power plants. Among the various devices designed to harness nuclear fusion, the tokamak confines the fusion fuel, w ...

Autonomous nuclear reactor monitoring is a key aspect of the International Atomic Energy Agency’s strategy to ensure nonproliferation treaty compliance. From the rise of small modular reactor technology, decentralized nuclear reactor fleets may strain the ...

Nuclear power is a powerful technology that plays an important role in the fight against climate change, and research is continuously engaged in studies that could further improve its safety. After the Fukushima accident, Accident Tolerant Fuels research h ...

Efforts are underway worldwide to develop advanced simulation methods of nuclear power plants, with an improved resolution in space, angle and energy. These tools aim to enhance operational efficiency through the predictions of local phenomena critical for ...

This paper presents simulations of Reactivity Initiated Accident on PWR fuel rods performed with two fuel performance codes: ALCYONE and OFFBEAT. These simulations were carried out in the framework of the first phase of the High-Burnup Experiments of React ...

This paper presents nuclear reactor transient measurements with thermal feedback and corresponding coupled neutronic-thermohydraulic simulations performed for the natural circulation cooled Training Reactor of Budapest University of Technology and Economic ...

Measurements of scalar flux distributions with fine spatial and energy resolutions are needed to remedy one of the validation shortcomings of the novel neutronics full core solvers, such as MPACT and nTRACER. While a very detailed resolution of the flux ca ...

Predicting particle transport in turbulent flows has a plethora of applications, some of which are: the transport of atmospheric aerosols, the deposition of blood cells in the arteries of human bodies and the atomization of fuel droplets in combustion cham ...

Cesium evaporation, aimed at enhancing the production of negative ions, has recently started during the last experimental campaigns in Source for the Production of Ions of Deuterium Extracted from a Radio frequency plasma (SPIDER). In view of the full-scal ...

This work presents a data-driven Reduced-Order Model (ROM) for parametric convective heat transfer problems in porous media. The intrusive Proper Orthogonal Decomposition aided Reduced-Basis (POD-RB) technique is employed to reduce the porous medium formul ...

The OpenFOAM Fuel BEhavior Analysis Tool, or OFFBEAT, is a multi-dimensional fuel performance code under collaborative development at the Laboratory for Reactor Physics and Systems Behaviour (LRS) of the EPFL and at the PSI. The code can be used both for s ...

In this study, an optimization of the canister loading for used nuclear fuels is performed, solely based on their decay heat values. By taking into account the individual irradiation history for each fuel assembly, as well as with a number of assumptions o ...

The European DEMOnstration Fusion Power Plant (EU-DEMO) is being designed as an intermediary stage between the ITER experimental reactor and future commercial fusion power plants. The EU-DEMO is based on the tokamak concept with a fully superconducting mag ...

Advancing Multi-Dimensional Simulation of Nuclear Fuel Behavior: from LOCA Analysis to Fast Reactor Applications

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Implementation of an Iter-relevant Qp-based Current Limit Avoidance Algorithm in the Tcv Tokamak

Assessment of JEFF Nuclear Data Libraries for Reactor Physics and Spent Fuel Composition Applications

Investigation of Hydrogen Behaviour in Irradiated Zirconium-Based Fuel Claddings by Neutron Imaging and Complementary Techniques

Multi-physics Sub-pin Resolution Analysis of a PWR core with nTRACER/CTF for the OECD/NEA TVA Watts Bar 1 Benchmark

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Investigation of scrape-off layer and divertor transport using infrared thermography and SOLPS-ITER simulations

Gamma noise to non-invasively monitor nuclear research reactors

Innovative thermophysical characterization of an ATF composite cladding: the case of silicon carbide

Validation of Intrapin Reaction Rate Distributions from Deterministic Transport Codes

Investigation of the PCMI failure of pre-hydrided Zy-4 cladding during Reactivity Initiated Accidents with ALCYONE and OFFBEAT fuel performance codes

Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor

Development of a High Fidelity Model of the CROCUS Experimental Reactor

On the Capability of Wall-Modeled Large Eddy Simulations to Predict Particle Dispersion in Complex Turbulent Flows

A Temperature Programmed Desorption Diagnostic for SPIDER Cs Operations

Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media

The OFFBEAT multi-dimensional fuel behavior solver

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Quench analysis of the DEMO CS1 coil