Search Results - "Sánchez Espinoza, Victor Hugo"
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The EC MUSA Project on Management and Uncertainty of Severe Accidents: Main Pillars and Status
Published in Energies (Basel) (01-08-2021)“…In the current state of maturity of severe accident codes, the time has come to foster the systematic application of Best Estimate Plus Uncertainties (BEPU) in…”
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Time discretization sensitivity analysis for a rod ejection transient scenario in a generic SMR concept using Serpent/SUBCHANFLOW
Published in EPJ Web of conferences (2024)“…This paper analyses a control rod ejection transient scenario in a generic SMR concept using the multi-physics coupling tool which includes the Monte Carlo…”
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High-Fidelity Steady-State and Transient Simulations of an MTR Research Reactor Using Serpent2/Subchanflow
Published in Energies (Basel) (01-02-2022)“…In order to join efforts to develop high-fidelity multi-physics tools for research reactor analysis, the KIT is conducting studies to modify the coupled…”
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4
Assessing the impact of DIONISIO-SubChanFlow code coupling in nuclear fuel performance simulations
Published in Nuclear engineering and technology (01-11-2024)“…Realistic simulation of nuclear fuel performance requires not only validated models capable of describing the thermomechanical phenomena that take place within…”
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Multiphysics modeling of a reactivity insertion transient at different fidelity levels in support to the safety assessment of a SMART-like small modular reactor
Published in Frontiers in energy research (26-05-2023)“…Typical design basis accidents such as the control Rod Ejection Accident (REA) will need to be evaluated during the safety analysis in support the licensing…”
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6
Verification of the Parallel Transport Codes Parafish and AZTRAN with the TAKEDA Benchmarks
Published in Energies (Basel) (01-04-2022)“…With the increase in computational resources, parallel computation in neutron transport codes is inherent since it allows simulations with high spatial-angular…”
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Validation of NEPTUNE-CFD Two-Phase Flow Models Using Experimental Data
Published in Science and technology of nuclear installations (01-01-2014)“…This paper deals with the validation of the two-phase flow models of the CFD code NEPTUNEC-CFD using experimental data provided by the OECD BWR BFBT and PSBT…”
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Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2.0
Published in Annals of nuclear energy (01-12-2017)“…•SAM efficiency during selected SBLOCAs in Konvoi PWR evaluated using ASTEC V2.0.•PSD must be initiated at CET=400°C or with a 20min delay to delay SA…”
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A New Coupled CFD/Neutron Kinetics System for High Fidelity Simulations of LWR Core Phenomena: Proof of Concept
Published in Science and technology of nuclear installations (01-01-2014)“…The Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technology (KIT) is investigating the application of the meso- and…”
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10
Investigation of SAM measures during selected MBLOCA sequences along with Station Blackout in a generic Konvoi PWR using ASTECV2.0
Published in Annals of nuclear energy (01-07-2017)“…•Reflooding is investigated for selected MBLOCA sequences in a Konvoi PWR using ASTEC.•After SBO, there is a grace time of 40min up to the detection of a…”
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11
Uncertainty and Sensitivity Studies with TRACE-SUSA and TRACE-DAKOTA by Means of Transient BFBT Data
Published in Science and technology of nuclear installations (01-01-2013)“…In the present paper, an uncertainty and sensitivity study is performed for transient void fraction and pressure drop measurements. Two transients have been…”
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12
Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0
Published in Annals of nuclear energy (01-03-2018)“…•Efficiency of SAM during SBO in Konvoi PWR is assessed using ASTECV2.0.•Secondary bleed/feed must be launched before CET > 400 °C and with 10 kg/s.•Primary…”
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Uncertainty and Sensitivity Studies with TRACE-SUSA and TRACE-DAKOTA by Means of Steady State BFBT Data
Published in Science and technology of nuclear installations (01-01-2013)“…The subject of the present paper is the uncertainty and sensitivity studies for steady state BFBT results including pressure drop and void fraction…”
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14
Validation of ASTECV2.1 based on the QUENCH-08 experiment
Published in Nuclear engineering and design (01-04-2017)“…•ASTECV2.1 can reproduce QUENCH-08 experimental trends e.g. hydrogen generation.•Radial temperature gradient and heat transfer through argon gap are…”
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Review and proposal for heat transfer predictions at supercritical water conditions using existing correlations and experiments
Published in Nuclear engineering and design (01-06-2011)“…► Implementation of heat transfer correlations for supercritical water into TRACE. ► Simulation of several heat transfer experiments with modified TRACE…”
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Analysis of MBLOCA and LBLOCA success criteria in VVER-1000/V320 reactors: New proposals for PSA Level 1
Published in Nuclear engineering and technology (01-02-2023)“…The specific configuration of the safety systems in VVER-1000/V320 reactors allows a comprehensive study of the Loss of Coolant Accident (LOCA). In the present…”
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Validation of ASTEC2.1 using QUENCH-12 for VVER-Reactors
Published in Nuclear engineering and design (15-08-2022)“…•Oxidation phenomena and molten material relocation for a severe accident case.•Different cladding material composition of VVER plants can result as higher…”
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KIT Multi-scale thermal–hydraulic coupling methods for improved simulation of nuclear power plants
Published in Nuclear engineering and design (15-04-2023)“…•Multi-scale methods for coupling of thermal hydraulic codes.•Domain overlapping and domain decomposition approach.•Detailed CFD-models.•Validation of…”
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Implementation and validation of CHF-models in the two-phase porous-media code TWOPORFLOW
Published in Nuclear engineering and design (01-03-2022)“…•Extension of TWOPORFLOW with CHF correlations.•Validation of CHF-models with steady state data.•Validation of CHF-models with transient data.•Improved and…”
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Analysis of the consequences of a LBLOCA with SBO severe accident in a generic VVER-1000 by means of ASTEC and JRODOS codes
Published in Nuclear engineering and design (15-12-2022)“…•Phenomena inside and outside of the vessel have been demonstrated, and the release and transport of fission products in a severe accident have been…”
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