Gonzalo Jiménez Varas
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View article: Using Scenarios for Reducing Uncertainties in Biodiversity Conservation: From Global Targets to European Steppes
Using Scenarios for Reducing Uncertainties in Biodiversity Conservation: From Global Targets to European Steppes Open
Scenario analysis allows assessing how complex socio‐ecological systems might respond to different policy pathways. We used an expert‐based participatory approach to explore how four different European socio‐ecological scenarios could impa…
View article: Analyzing cryptocurrency volatility: an EGARCH model
Analyzing cryptocurrency volatility: an EGARCH model Open
The aim of this article is to examine the reasons why cryptocurrency volatility hinders its potential to replace fiat money as legal tender. We focus on Bitcoin and Ethereum for this analysis. By applying an augmented Dickey-Fuller station…
View article: Enhancing severe accident management through research
Enhancing severe accident management through research Open
After the Fukushima Daiichi accident, a new wave of research projects aiming at enhancing severe accident (SA) management was launched under different international frameworks. This was the case of MUSA (Management and Uncertainties of Sev…
View article: From past to future: The role of computational fluid dynamics in advancing nuclear safety in Spain and Portugal
From past to future: The role of computational fluid dynamics in advancing nuclear safety in Spain and Portugal Open
This document explores the role of CFD in nuclear safety studies, with a particular focus on advancements in Spain and Portugal. The field of nuclear safety has increasingly included CFD models to address complex safety–critical phenomena,…
View article: Optimization of prevention and mitigation of severe accidents through Research: Major outcomes and outlook of the Spanish programme
Optimization of prevention and mitigation of severe accidents through Research: Major outcomes and outlook of the Spanish programme Open
Severe accidents research activities in Spain have grown substantially since the Fukushima-Daiichi accident. Most of these research activities have been conducting by a few organizations (national research center and academia) with the sup…
View article: Spanish R&D in dry storage of spent fuel: Outcomes and outlook
Spanish R&D in dry storage of spent fuel: Outcomes and outlook Open
The Spanish R&D efforts in dry interim storage of spent nuclear fuel (SNF) are mainly focused on supporting safety under storage and transportation, including intermediate operations. Major actors involved are research entities, academia, …
View article: Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes
Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes Open
The dry storage of nuclear spent fuel is a common solution chosen by many nuclear power plants to store their fuel after depleting the nuclear spent fuel pool. The process of designing and licensing a cask is long and complicated. It is no…
View article: Assessment of the depressurization and mixing effects of two spray systems in the PANDA facility, part I – Experimental results
Assessment of the depressurization and mixing effects of two spray systems in the PANDA facility, part I – Experimental results Open
The spray safety system is one of the most effective solutions to limit the pressure and temperature rise in the containment of a nuclear power plant during a design basis accident. However, its actuation under severe accident conditions m…
View article: Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – Simulations using GOTHIC8.3(QA)
Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – Simulations using GOTHIC8.3(QA) Open
The spray safety system is one of the most effective solutions to limit the pressure and temperature rise in the containment of a nuclear power plant during a design basis accident. However, its actuation under severe accident conditions m…
View article: Towards an optimized management of accidents
Towards an optimized management of accidents Open
Nuclear safety has been one of the main research domains in EURATOM programs for decades, and accident prevention and mitigation have drawn much of the attention paid over the years to this framework. In the essence of this interest are de…
View article: PARUPM: A simulation code for passive auto-catalytic recombiners
PARUPM: A simulation code for passive auto-catalytic recombiners Open
In the event of a severe accident with core damage in a water-cooled nuclear reactor, combustible gases (H 2 and possibly CO) get released into the containment atmosphere. An uncontrolled combustion of a large cloud with a high concentrati…
View article: Modeling Validation Exercises Using the Dry Cask Simulator
Modeling Validation Exercises Using the Dry Cask Simulator Open
The U.S. Department of Energy (DOE) established a need to understand the thermal-hydraulic properties of dry storage systems for commercial spent nuclear fuel (SNF) in response to a shift towards the storage of high-burnup (HBU) fuel (> 45…
View article: 3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code
3D containment modeling of PWR-KWU Trillo NPP with the GOTHIC code Open
Containment safety analysis is a field in expansion given the complex phenomenology developed during an accident, and the recent code capabilities improvement. In this paper, a modeling strategy to create complex containments with porous C…
View article: THERMAL STUDY OF SEVERAL SPENT FUEL CASK DISTRIBUTIONS IN A REPOSITORY USING CFD CODES
THERMAL STUDY OF SEVERAL SPENT FUEL CASK DISTRIBUTIONS IN A REPOSITORY USING CFD CODES Open
Peak Cladding Temperature (PCT) becomes the reference parameter when assessing the safety during the spent fuel drystorage phase and is dependent on the overall thermal performance. Many variables have been studied in the literature, inclu…
View article: Three-dimensional simulation of a LBLOCA in an AP1000® containment building
Three-dimensional simulation of a LBLOCA in an AP1000® containment building Open
AP1000® is a Generation III+ reactor in which all safety systems relay on passive elements. AP1000 containment includes an In-containment Refueling Water Storage Tank (IRWST), a stainless steel liner that acts as a heat sink, and a Passive…