Desarrollo e un simulador termohidráulico informático para PWRs basado en RELAP5/Mod3

La presente tesis consiste en el desarrollo de un proyecto de simulador termohidráulico para PC, tipo "analizador de planta" de una central PWR (C.N.Trillo) con aportaciones originales en cada uno de los hitos fundamentales que deben ser cubiertos en un trabajo de estas características: 1. Control de la configuración del simulador. 2. Desarrollo del modelo de simulación. 3. Validación del simulador. La inclusión de interactividad sobre componentes activos permite al personal no especializado en el uso de códigos de simulación, estudiar de forma simple la efectividad de las actuaciones previstas y su fundamento físico. Además con la ampliación de la simulación numérica orientada a la operación y la nueva interfase gráfica es posible visualizar claramente el decurso físico de un transitorio por medio de colores cambiantes, niveles móviles, alarmas, etc. El alto grado de ajuste a la respuesta estacionaria y transitoria de la planta queda comprobada a través del cumplimiento de los estrictos requisitos de validación numérica frente a datos reales de 4 transitorios de planta. Por tanto, las características de manejo y fiabilidad del nuevo simulador facilitan su uso como herramienta de ingeniería y permiten su utilización directa en cursos de formación de operadores o personal no especializado en simulación

Análisis de acciones del operador en un SBLOCA de 1”en el fondo de la Vasija en un Reactor tipo PWR

La simulación de accidentes de rotura pequeña en el fondo de la vasija se aparta del convencional análisis de LOCA de rama fría, el más limitante en los análisis deterministas La rotura de una de las penetraciones de instrumentación de la vasija ha sido desestimada históricamente en los análisis de licencia y en los Análisis Probabilistas de Seguridad y por ello, hay una falta evidente de literatura para dicho análisis. En el año 2003 durante una inspección, se detectó una considerable corrosión en el fondo de la vasija de South Texas Project Unit I NPP. La evolución en el tiempo de dicha corrosión habría derivado en una pequeña rotura en el fondo de la vasija si su detección no se hubiera producido a tiempo. La OECD/NEA consideró la importancia de simular dicha secuencia en la instalación experimental ROSA, la cual fue reproducida posteriormente por grupos de investigación internacionales con varios códigos de planta. En este caso el código utilizado para la simulación de las secuencias experimentales es TRACE. Tanto en el experimento como en la simulación se observaron las dificultades de reinundar la vasija al tener la rotura en el fondo de la misma, haciendo clave la gestión del accidente por parte del operador. Dadas las condiciones excesivamente conservadoras del test experimental, como el fallo de los dos trenes de inyección de alta presión durante todo el transitorio, en las aplicaciones de los experimentos con modelo de Almaraz NPP, se ha optado por reproducir dicho accidente con condiciones más realistas, verificando el impacto en los resultados de la disponibilidad de los trenes de inyección de alta presión o los tiempos de las acciones manuales del operador, como factores más limitantes y estableciendo el diámetro de rotura en 1

Análisis de Estimación Óptima del Accidente de Pérdida de Refrigerante por Rotura Pequeña de 1”en Cabeza de Vasija en un Reactor tipo PWR

En el año 2002 durante una inspección se localizó una importante corrosión en la cabeza de la vasija de Davis Besse NPP. Si no se hubiera producido esa detección temprana, la corrosión hubiera provocado una pequeña rotura en la cabeza de la vasija. La OECD/NEA consideró la importancia de simular esta secuencia en la instalación experimental ROSA, la cual fue reproducida posteriormente por grupos de investigación internacionales con varios códigos de planta. En este caso el código utilizado para la simulación de las secuencias experimentales es TRACE. Los resultados de este test experimental fueron muy analizados internacionalmente por la gran influencia que dos factores tenía sobre el resultado: las acciones del operador relativas a la despresurización y la detección del descubrimiento del núcleo por los termopares que se encuentran a su salida. El comienzo del inicio de la despresurización del secundario estaba basado en la determinación del descubrimiento del núcleo por la lectura de los temopares de salida del núcleo. En el experimento se registró un retraso importante en la determinación de ese descubrimiento, comenzando la despresurización excesivamente tarde y haciendo necesaria la desactivación de los calentadores que simulan el núcleo del reactor para evitar su daño. Dada las condiciones excesivamente conservadoras del test experimentale, como el fallo de los dos trenes de inyección de alta presión durante todo el transitorio, en las aplicaciones de los experimentos con modelo de Almaraz NPP, se ha optado por reproducir dicho accidente con condiciones más realistas, verificando el impacto en los resultados de la disponibilidad de los trenes de inyección de alta presión o los tiempos de las acciones manuales del operador, como factores más limitantes y estableciendo el diámetro de rotura en 1

Simulación del accidente de SGTR en un PWR-W con TRACE para distintas metodologías de análisis determinista de seguridad

A Steam Generator Tube Rupture (SGTR) in a Pressurized Water Reactor (PWR) can lead to an atmospheric release bypassing the containment via the secondary system and exiting though the Pressurized Operating Relief Valves of the affected Steam Generator. That is why SGTR historically have been treated in a special way in the different Deterministic Safety Analysis (DSA), focusing on the radioactive release more than the possibility of core damage, as it is done in the other Loss of Coolant Accidents(LOCAs)

Desarrollo de modelos 3D de los edificios de contención de la Central Nuclear de Almaraz y de la Central Nuclear de Trillo con el código GOTHIC 8.0

El análisis de los accidentes tipo LOCA o MSLB en una contención PWR-W normalmente se simulan con la opción de volúmenes de control con parámetros agrupados en GOTHIC, ya que es lo que hasta ahora se ha considerado adecuado para el análisis de licencia. Sin embargo, para el estudio de detalle del comportamiento termo-hidráulico de cada recinto de la contención, podría ser más adecuado contar con un modelo tridimensional que representase más fielmente la geometría de la contención. El objetivo de la primera fase del proyecto de investigación de CNAT y la UPM es la construcción de varios modelos tridimensionales detallados con el código GOTHIC 8.0 de los edificios de contención de una planta tipo PWR-W y KWU, correspondientes a la Central Nuclear de Almaraz (CNA) y Trillo (CNT) respectivamente

Three-dimensional Containment Accident Analysis using different approaches in Almaraz NPP

Containment Design Basis Accident analysis are usually performed using lumped-parameters models as this kind of models do not require high computational resources. Moreover, they offer overall good results of average pressure and temperature evolution. However, in order to perform a detailed local analysis, a thermal-hydraulic behavior study of every containment room may be necessary. To achieve this goal, a more detailed containment 3D model is imperative for capturing the local phenomena which occurs during a mass and energy release accident. During the last years in the collaborative project between the UPM and CNAT, several Almaraz NPP containment 3D models have been developed. The most precise one, called Detailed Integral Model, is able to obtain results with a very high resolution. However, this approach requires also high computational resources. For this reason two new models, called Multi-Zone Models, were developed with a coarser nodalization and therefore a lower computational requirement is needed. In this paper, the new modeling approach is described. A LBLOCA has been simulated in the Multi-Zone Model and it has been compared with the results obtained from the Detailed Integral Model. After analyzing the results, it can be concluded that the thermal-hydraulic evolutions are similar although the local variables differ in some cases. Taking into account the differences between models, a criteria in the use of the different approaches described has been stated depending on the analysis objective

Double-Ended LBLOCA Containment Analysis in Trillo NPP with GOTHIC 8.1

The radioactive material confinement in a nuclear power plant (NPP), , is a fundamental safety function to be ensured during a design basis accident (DBA). For plant licensing analysis, the containment is usually modeled with a lumped parameter approach. The assumption that within each region the fluid is well mixed is inherent to this approach. However, the containment is a large building with a complex configuration. It is distributed in several compartments that avoid the well mixing of the fluid and that provoke three-dimensional effects that affect the thermal–hydraulic behavior. Reactors like Trillo NPP are highly compartmentalized in order to reduce the dose to the personnel, in contrast with PWR-W reactors that present a more diaphanous layout. Accordingly, this kind of reactors are more liable to have three dimensional effects and/or local differences than a PWR-W. The collaborative project between the UPM and CNAT has enabled the development of highly detailed three-dimensional models of the Trillo NPP containment building. The objective of this study is the detailed 3D thermal-hydraulic analysis during a mass and energy release where local effects can be observed. Most of DBA analysis are performed using lumped-parameters models which only allow to know the average containment state, and that has several assumptions related with 0D models. For this reason a generic double-ended LBLOCA is simulated in a GOTHIC 3D model in order to study the local phenomenology occurring during this kind of transient. Analyzing the results, an homogeneous pressurization over the whole containment can be observed, with the exception of the rooms near the break. This is predictable given that pressure is transmitted at the speed of sound. However, temperature evolution is different between compartments. Temperature behavior obeys to convective-diffusive processes, and it presents strong differences between compartments that cannot be seen with lumped parameters models. The steam residence time becomes one of the critical parameters in the containment thermal behavior, and this is strongly dependent on the building geometry

Evaluating the extent and impact of the extreme Storm Gloria on Posidonia oceanica seagrass meadows

Extreme storms can trigger abrupt and often lasting changes in ecosystems by affecting foundational (habitat-forming) species. While the frequency and intensity of extreme events are projected to increase under climate change, its impacts on seagrass ecosystems remain poorly documented. In January 2020, the Spanish Mediterranean coast was hit by Storm Gloria, one of the most devastating recent climate events in terms of intensity and duration. We conducted rapid surveys of 42 Posidonia oceanica meadows across the region to evaluate the extent and type of impact (burial, unburial and uprooting). We investigated the significance of oceanographic (wave impact model), geomorphological (latitude, depth, exposure), and structural (patchiness) factors in predicting impact extent and intensity. The predominant impact of Storm Gloria was shoot unburial. More than half of the surveyed sites revealed recent unburial, with up to 40 cm of sediment removed, affecting over 50 % of the meadow. Burial, although less extensive, was still significant, with 10–80 % of meadow cover being buried under 7 cm of sediment, which is considered a survival threshold for P. oceanica. In addition, we observed evident signs of recently dead matte in some meadows and large amounts of detached drifting shoots on the sea bottom or accumulated as debris on the beaches. Crucially, exposed and patchy meadows were much more vulnerable to the overall impact than sheltered or continuous meadows. Given how slow P. oceanica is able to recover after disturbances, we state that it could take from decades to centuries for it to recoup its losses. Seagrass ecosystems play a vital role as coastal ecological infrastructure. Protecting vulnerable meadows from anthropogenic fragmentation is crucial for ensuring the resilience of these ecosystems in the face of the climate crisis.This study was funded by the CSIC project “Effects of storm Gloria on the western Mediterranean meadows (202030E052) and “Storms of change: as phenomena extreme weather alters Mediterranean coastal ecosystems, their services and their perception by society" (PID2020-113745RB-I00), state program of I+D+I Oriented to the Challenges of the Society and within the framework of the activities of the Spanish Government through the "Maria de Maeztu Centre of Excellence” accreditation to IMEDEA (CSIC-UIB) (CEX2021-001198). We want to thank the SPAS (Society of Fishing and Underwater Activities of Mataró) and the Mataró City Council, which has financed 25 years of the Alguer de Mataró project

Multicentric study of cervical cancer screening with human papillomavirus testing and assessment of triage methods in Latin America : the ESTAMPA screening study protocol

Q1Q1Introduction Human papillomavirus (HPV) testing is replacing cytology in primary screening. Its limited specificity demands using a second (triage) test to better identify women at high-risk of cervical disease. Cytology represents the immediate triage but its low sensitivity might hamper HPV testing sensitivity, particularly in low-income and middle-income countries (LMICs), where cytology performance has been suboptimal. The ESTAMPA (EStudio multicéntrico de TAMizaje y triaje de cáncer de cuello uterino con pruebas del virus del PApiloma humano; Spanish acronym) study will: (1) evaluate the performance of different triage techniques to detect cervical precancer and (2) inform on how to implement HPV-based screening programmes in LMIC. Methods and analysis Women aged 30–64 years are screened with HPV testing and Pap across 12 study centres in Latin America. Screened positives have colposcopy with biopsy and treatment of lesions. Women with no evident disease are recalled 18 months later for another HPV test; those HPV-positive undergo colposcopy with biopsy and treatment as needed. Biological specimens are collected in different visits for triage testing, which is not used for clinical management. The study outcome is histological high-grade squamous intraepithelial or worse lesions (HSIL+) under the lower anogenital squamous terminology. About 50 000 women will be screened and 500 HSIL+ cases detected (at initial and 18 months screening). Performance measures (sensitivity, specificity and predictive values) of triage techniques to detect HSIL+ will be estimated and compared with adjustment by age and study centre. Ethics and dissemination The study protocol has been approved by the Ethics Committee of the International Agency for Research on Cancer (IARC), of the Pan American Health Organisation (PAHO) and by those in each participating centre. A Data and Safety Monitoring Board (DSMB) has been established to monitor progress of the study, assure participant safety, advice on scientific conduct and analysis and suggest protocol improvements. Study findings will be published in peer-reviewed journals and presented at scientific meetings. Trial registration number NCT01881659Revista Internacional - Indexad