Testing the NURESIM platform on a PWR main steam line break benchmark

Abstract

Within the NURESAFE project, a main steam line break benchmark has been defined and solved by codes integrated into the European code platform NURESIM. The paper describes the results of the calculations for this benchmark. Six different solutions using different codes and code systems are provided for the comparison. The quantitative differences in the results are dominated by the differences in the secondary system parameters during the depressurization. The source of these differences comes mainly from the application of different models for the two-phase leak flow available in the system codes. The use of two different thermal hydraulic system codes influences the results more than expected when the benchmark was created. The codes integrated into the NURESIM platform showed their applicability to a challenging transient like a main steam line break.

Generación de librerías optimizadas con cuantificación de incertidumbres para cálculos realistas (BEPU) de reactores nucleares de agua ligera

“…• Generación de librerías avanzadas de secciones eficaces, incluyendo factores de discontinuidad por interfaz y factores de reconstrucción de potencia, a escala nodal y de celda para su aplicación en la simulación de transitorios en reactores PWR y VVER [73,120,119,76,117].…”

“…Las especificaciones del problema se definen en uno de los deliverables del proyecto [85] y en [73]. Están basadas en el benchmark del PWR M OX/U O 2 por lo que el reactor de referencia es el mismo que en la sección anterior.…”

Study and lmplementation of Neutronic-Thermohydraulic Coupling Methods for Detailed Analysis of Transients in Nuclear Reactors for Safety Margins Optimization

“…Due to the characteristics of the computing platform, this coupling can be performed using different spatial meshes for the thermalhydraulic and neutronic calculations being the interpolation task transparent for the user. In this way, different resolutions at NK and TH physics can be tested or used for operational or safety analyses (García-Herranz et al 2017) , (Spasov et al 2017) , (Kliem et al 2017).…”

“…• DYN3D and SUBCHANFLOW (Daeubler et al 2015) • CATHARE2 and FLICA-IV (Kliem et al 2017) • DYN3D and COBRA-TF (Périn and Velkov 2017) OS splitting is the easiest mode to develop coupling. There are other methodologies which are based on the OS and supposes an improvement of it.…”

“…NURESIM platform integrates the codes for simulation of different aspects of the nuclear reactor providing the following capabilities (Kliem et al 2017):…”