Results 1 to 10 of about 10,212 (309)

CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development

open access: yesEnergies, 2021
Simulation codes allow one to reduce the high conservativism in nuclear reactor design improving the reliability and sustainability associated with nuclear power.
Sebastian Davies   +8 more
doaj   +3 more sources

NEUTRON EMISSION MEASUREMENTS OF PWR SPENT FUEL SEGMENTS AND PRELIMINARY VALIDATION OF DEPLETION CALCULATIONS [PDF]

open access: yesEPJ Web of Conferences, 2021
Assessing neutron emission of LWR spent fuel is necessary for the back-end of the fuel cycle, such as the dimensioning of transport and storage casks of spent fuel.
Perret G.   +3 more
doaj   +1 more source

In search of the best nuclear data file for proton induced reactions: Varying both models and their parameters [PDF]

open access: yesEPJ Web of Conferences, 2020
A lot of research work has been carried out in fine tuning model parameters to reproduce experimental data for neutron induced reactions. This however is not the case for proton induced reactions where large deviations still exist between model ...
Alhassan E.   +6 more
doaj   +1 more source

Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations [PDF]

open access: yesEPJ Web of Conferences, 2020
The international experimental program PETALE will be carried out at the CROCUS research reactor of EPFL. The program aims at measuring neutron penetration in slabs made of materials composing typical LWR reactor pressure vessel. The measurements will be
Vasiliev Alexander   +7 more
doaj   +1 more source

Towards a 100% renewable energy share for heating and cooling in office buildings with solar and geothermal energy

open access: yesSolar Energy Advances, 2022
An integrated energy system for office buildings is examined, with the use of a numerical tool that has been developed for simulating renewable energy-based systems based on geothermal and solar energy. The main system components are the PV-Thermal (PVT)
Marika Pilou   +3 more
doaj   +1 more source

A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments

open access: yesNuclear Engineering and Technology, 2022
The aim of this paper is to assess the reliability and accuracy of the PSI standard method, used in many previous works, for the quantification of ND uncertainties in the SPERT-III RIA transient, by quantifying the discrepancy between the actual inserted
A. Dokhane   +4 more
doaj   +1 more source

Modeling of an Integrated Renewable-Energy-Based System for Heating, Cooling, and Electricity for Buildings

open access: yesEnergies, 2023
An integrated numerical model that describes the operation of a renewable-energy-based system for a building’s heating, cooling, and domestic hot water needs is described in this study. The examined energy system includes a vapor compression multi-source
Marika Pilou   +2 more
doaj   +1 more source

NEUTRON NOISE SPECTRAL FEATURES OF SIMULATED MECHANICAL AND THERMAL-HYDRAULIC PERTURBATIONS IN A PWR CORE [PDF]

open access: yesEPJ Web of Conferences, 2021
KWU-PWR reactors (SIEMENS design) are commonly exhibiting high neutron noise levels that can lead to costly operational issues. Recent analysis seems to indicate that, coolant flow, temperature oscillations, and mechanical vibrations have a key impact on
Torres L.A   +4 more
doaj   +1 more source

CONTRIBUTION OF THERMAL-HYDRAULICS SIMULATION TO CRITICALITY ANALYSIS OF A DEBRIS BED NUMERICAL MOCK-UP [PDF]

open access: yesEPJ Web of Conferences, 2021
In this work, we evaluate the impact of simulating the thermal-hydraulics feedback in criticality risk assessment in a benchmark configuration corresponding to a simplified debris bed.
Boulard P.   +3 more
doaj   +1 more source

MULTI-PHYSICS TRANSIENT SIMULATIONS WITH TRIPOLI-4® [PDF]

open access: yesEPJ Web of Conferences, 2021
In this work, we present the first dynamic calculations performed with the Monte Carlo neutron transport code TRIPOLI-4R with thermal-hydraulics feedback.
Faucher Margaux   +2 more
doaj   +1 more source

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