3D analysis of spray effect on long-term depressurization of VVER-1000 containment during LB-LOCA

ME Kanik, O Noori-kalkhoran, M Gei… - Progress in Nuclear …, 2024 - Elsevier
Containment as the last barrier of defence in depth strategy plays the most important role in
protecting the environment and public from the release of radioactive material. As a result …

Full scope 3D analysis of a VVER-1000 containment pressurization during a LB-LOCA by employing AutoCAD and GOTHIC code

ME Kanik, O Noori-kalkhoran… - Progress in Nuclear …, 2022 - Elsevier
One of the main goals of severe accident management strategies is to maintain containment
integrity to prevent radioactive release into the environment. As a result, containment …

AP1000 Passive Containment Cooling System study under LBLOCA conditions using the GOTHIC code

S Estévez-Albuja, K Fernández-Cosials… - … Engineering and Design, 2021 - Elsevier
Abstract AP1000® Generation III+ reactor bases its safety concept on passive systems,
differently from the previous Generation II reactors. This fact has led the approximations and …

[HTML][HTML] Comparisons of performance and operation characteristics for closed-and open-loop passive containment cooling system design

J Bang, DW Jerng, H Kim - Nuclear Engineering and Technology, 2021 - Elsevier
Passive containment cooling systems (PCCSs) have been actively studied to improve the
inherent safety of nuclear power plants. Hered, we present two concepts, open-loop PCCS …

[HTML][HTML] From past to future: The role of computational fluid dynamics in advancing nuclear safety in Spain and Portugal

Y Rivera, A Escrivá, C Berna, E Vela… - … Engineering and Design, 2024 - Elsevier
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 …

[HTML][HTML] The Preventive Methodology: A priori modification of the containment geometry to boost the computational efficiency of GOTHIC 3D models

C Vázquez-Rodríguez, G Jiménez… - … Engineering and Design, 2025 - Elsevier
Historically, the deterministic safety analysis simulations for large dry containments of
operating nuclear power plants have been done with nuclear legacy codes using the …

Study of hydrogen risk in a PWR-W containment during a SBO scenario; Tau parameter definition and application on venting strategy analysis

K Fernández-Cosials, G Jimenez, R Bocanegra… - … Engineering and Design, 2017 - Elsevier
Hydrogen management is still one of the main nuclear safety topics because of its violent
reaction with oxygen. During a severe accident, hydrogen can be generated and it can be …

[HTML][HTML] Optimization of prevention and mitigation of severe accidents through Research: Major outcomes and outlook of the Spanish programme

LE Herranz, A Domínguez-Bugarín… - … Engineering and Design, 2024 - Elsevier
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 …

Evaluation of the reactor building environmental conditions under a LOCA for the decommissioning Chinshan plant

YS Chen, LY Huang - Annals of Nuclear Energy, 2021 - Elsevier
Both units of the Chinshan plant have been approved for decommissioning. However, fuel
assemblies cannot be discharged from the reactor core because the spent fuel pool (SFP) is …

Accident influence to the thermal conditions of the main buildings of the Kuosheng plant during the decommissioning process

A Lin, LY Huang, YS Chen - Nuclear Engineering and Design, 2022 - Elsevier
The Kuosheng plant has two BWR/6 units and unit 1 has started the decommissioning
process. The fuel assemblies are staying inside the reactor vessel due to insufficient space …