Post-test calculation and uncertainty analysis of the experiment QUENCH-07 with the system code ATHLET-CD

Austregesilo, H.; Bals, Christine; Trambauer, K.

doi:10.1016/j.nucengdes.2007.02.019

Cited by 9 publications

(3 citation statements)

References 4 publications

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“…The thermal-hydraulic system code ATHLET [9,10] is developed by the Gesellschaft fuer Anlagen-und Reaktorsicherheit gGmbH (GRS). The highly modular code structure of ATHLET includes advanced thermal-hydraulics as well as physical and numerical models.…”

Section: Codes and Methods Description • The Thermal-hydraulic System...mentioning

confidence: 99%

Codes and methods improvements for safety assessment and LTO: varied approaches

Cagnac¹,

Verrier²,

Pistora

2023

EPJ Nuclear Sci. Technol.

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Nuclear safety has always been at the heart of the concerns of nuclear power plant operators and developers, as well as of various nuclear research organizations and regulatory authorities. Over the last decades, all these nuclear actors have developed and integrated a large number of calculation codes and other tools into their safety work. From the system approach to the local understanding of a phenomenon on a given component, from neutronics to operation optimization for long-term operation, these methods and codes have been constantly evolving since their appearance, in order to be able to integrate new plant designs and components, to improve the results of modeling physical phenomena or quantify and thus reduce the uncertainties on these results. Currently, several H2020 Euratom projects are working on the improvement of these codes and methods. This article will focus on three of these projects: CAMIVVER (Codes And Methods Improvements for VVER comprehensive safety assessment), APAL (Advanced PTS Analysis for LTO), and sCO2-4-NPP (innovative SCO2-based heat removal technology for an increased level of safety of Nuclear Power Plants) in order to illustrate our thinking on the improvement of calculation frameworks. First, we will present the work and the approach adopted with regard to the different calculation codes and methods used in each of these three projects. We will then conclude with an overall analysis of these three approaches, highlighting the difficulties and successes of these three projects, and identifying areas of work for the general improvement of the calculation codes.

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Section: Codes and Methods Description • The Thermal-hydraulic System...mentioning

confidence: 99%

Codes and methods improvements for safety assessment and LTO: varied approaches

Cagnac¹,

Verrier²,

Pistora

2023

EPJ Nuclear Sci. Technol.

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“…Analysis of thermal-hydraulics of leaks and transients with core degradation is developed by Gasellschaft fur Anlagen und Reaktorsicherheit (GRS) in cooperation with IKE in Germany (Trambauer and Austregesilo, 2003;Austregesilo et al, 2007;Hollands et al, 2007;Repetto et al, 2007). The ATHLET code can be used to predict a spectrum of beyond design-basis accidents for BWRs and PWRs, but without core degradation.…”

Section: Code Development Review and Relevant Applicationsmentioning

confidence: 99%

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Wang

Shi

et al. 2018

Front. Energy Res.

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“…The current plant thermalhydraulics code use two-phase flow models. The most used plant codes are the European codes ATHLET [67] and CATHARE [68] and the code developed by the US Nuclear Regulatory Commission (NRC) TRACE [69]. TRACE was created to merge and extend the capabilities of the 3 NRC legacy safety codes: TRAC-P, TRAC-B and RELAP.…”

Section: Plant Codesmentioning

confidence: 99%

Monte Carlo Neutronics and Thermal-hydraulics coupling applied to Fast Reactors

Antolín¹

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El trabajo de esta tesis ha sido financiado mediante una beca de formación de personal investigador del Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT) durante el periodo 2009-2013. La estancia de seis meses en el 'Institute for Energy and Transport' del 'EU Joint Research Centre' en Petten (Holanda) fue financiada por la Comisión Europea a través de su programa de prácticas (in-service training). La investigación desarrollada se enmarca en la participación del CIEMAT en los proyectos CDT-FASTEF y MAXSIMA del 7º Programa Marco de la Unión Europea, así como en el programa de colaboración CIEMAT-ENRESA.Son muchas las personas que, de una u otra forma, han hecho posible este trabajo y a las que desearía mostrar mi reconocimiento a través de estas breves líneas.En primer lugar, me gustaría dar las gracias a Francisco Martín-Fuertes, mi director de tesis, por darme la oportunidad de realizar este trabajo, por su dedicación a mi formación durante estos más de cuatro años, por haberme enseñado esa parte de ingeniería que nos falta a los físicos, por su apoyo, ánimo y consejo en los momentos más difíciles y sobre todo, por la confianza depositada en mi desde el primer momento.Quisiera, además dar las gracias a Enrique Gonzalez, jefe de la División de Fisión del CIEMAT, por haberme abierto las puertas de esta institución, por compartir sus conocimientos y por la ayuda prestada, en especial en la última parte de la tesis. A mis compañeros de la Unidad de Innovación Nuclear del CIEMAT, por contribuir al desarrollo de este trabajo y, en particular, a Paco Álvarez, por su disponibilidad e inestimable ayuda para resolver cualquier duda con MCNP, así como con la revisión de la tesis. A David Villamarín, por compartir conmigo todo su conocimiento sobre neutrones retardados. Y a Emilio Mendoza, por ser un compañero de despacho tan paciente, por su ayuda con C++ y por las charlas sobre física y sobre la vida en general. No olvido tampoco al resto de mis compañeros (

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Post-test calculation and uncertainty analysis of the experiment QUENCH-07 with the system code ATHLET-CD

Cited by 9 publications

References 4 publications

Codes and methods improvements for safety assessment and LTO: varied approaches

Codes and methods improvements for safety assessment and LTO: varied approaches

Review on Core Degradation and Material Migration Research in Light-Water Reactors

Monte Carlo Neutronics and Thermal-hydraulics coupling applied to Fast Reactors

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