Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB

Daeubler, Miriam; Trost, Nico; Jiménez, Javier López; Sánchez, V.; Macián‐Juan, Rafael

doi:10.1016/j.anucene.2014.09.057

Cited by 19 publications

(6 citation statements)

References 26 publications

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“…The total rod worth is also provided. For additional comparison, MCNP results from Reference Kozlowski et al (2006) are provided as well as pin-by-pin results from the diffusion theory code COBAYA3 and the SP 3 code DYNSUB from Reference Daeubler et al (2015). The EWE and PWE of the relative differences in the assembly powers is also provided in Table 3.…”

Section: Rodded Resultsmentioning

confidence: 97%

“…Table 1 shows the results of the eigenvalues of the three NEM calculations compared with the reference solution of the multigroup transport code DeCART as well as the mean deviations of the fuel assembly powers from the reference DeCART solution. For additional comparison, MCNP results from Reference Kozlowski et al (2006) are also provided as well as pin-by-pin results from the diffusion theory code COBAYA3 and the SP 3 code DYNSUB from Reference Daeubler et al (2015). The measurements of the error in the fuel assembly powers use the Kozlowski et al (2006), the PWE and the EWE.…”

Section: All Rods Out Resultsmentioning

confidence: 98%

“…The results are presented in Table 2 below. The DYNSUB results from Reference Daeubler et al (2015) are also included. A representative assembly (assembly A1) with the pin power % error for the three analytical methods is shown in Fig.…”

Section: All Rods Out Resultsmentioning

confidence: 99%

See 2 more Smart Citations

Advances in the Pennsylvania State University NEM code

Thompson

Ivanov

2016

Annals of Nuclear Energy

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Section: Rodded Resultsmentioning

confidence: 97%

Section: All Rods Out Resultsmentioning

confidence: 98%

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Advances in the Pennsylvania State University NEM code

Thompson

Ivanov

2016

Annals of Nuclear Energy

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“…Also COBAYA3/COBRA TF system developed at UPM has been used to carry out 3D core pin by pin diffusion calculations for steady states using a domain decomposition technique with alternate dissections (Herrero et al, 2009). More recently, DYN SUB code system (Daeubler et al, 2015), an internal coupling of the 3D neutron kinetics code DYN3D and the sub channel code SUBCHANFLOW, was used for static and transient pin by pin simulations of the OECD NEA and U.S. NRC PWR MOX/UO2 core transient benchmark (Kozlowski and Downar, 2003). The applicability for LWR transient analysis was demonstrated, although execution times were reported to remain too high for its routine application.…”

Section: Introductionmentioning

confidence: 99%

Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis

García-Herranz

Cuervo

Sabater

et al. 2017

Nuclear Engineering and Design

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At UPM, in depth modifications of the core simulator COBAYA, able to perform neutronics diffusion cal culations at both nodal and pin by pin levels, have been accomplished during the 7th Framework EURATOM NURESAFE project.The main goal was to upgrade its integration in the European Platform for Nuclea r Reactor Safety Simulation in order to facilitate the coupling with any other code of the platform for multi physics analysis, focusing also on the code legibility and maintainability. An external and flexible coupling with the thermal hydraulics code COBRA TF was designed. As a result, COBAYM/COBRA TF allows multiscale coupled calculations, enabling both nodal and pin by pin neutronics resolutions using both assembly based channels and pin based subchannels at the thermal hydraulics domain.flexible mapping schemes also in axial direction can be defined. The coupled system was applied to a Main Steam Line Break transient benchmark.Pin by pin 30 sim ulations using one thermal hydraulic channel per assembly were carried out in a reasonable computing time, and results compared to nodal solutions demonstrating the multiscale coupling capability for full core transients. Pin by pin calculations using thermal hydraulics subchannels will be performed in a near future to assess the role that a very detailed mapping can play to predict realistic local parameters. While in asymmetric transients the effect can be important, it is expected that in symmetric transients assembly based thermal hydraulics channels can provide accurate pin by pin solutions in execution times suitable for routine analysis. The performed work will bring the ability to explore in an easy way multiscale effects on safety tran sient evaluations and give recommenda tions for the neutronics/thermal hydraulics mapping depending on the application

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“…• 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.…”

Section: Operator Splitting Coupling Techniquementioning

confidence: 99%

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

Alcaráz¹

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Understanding the performance of a nuclear reactor is a complex task that covers different physical fields as the neutron behavior or fluid dynamics. These fields are not isolated, and there is a feedback among them. Along nuclear engineering history, different codes have been developed to analyze each of the physics in which the problem can be split in an isolated way. An example of this are the neutronic or the thermal-hydraulic codes. To study the performance of the reactor in a realistic way, it is necessary to take into account the interaction among the physics, or in other words, the codes have to be coupled. xiii ha facilitado en todo lo posible que pudiera seguir con mis estudios. Además, mis compañeros, Jorge, Paloma, Alfonso, Rosario, Carmen, Lustolde, David y Ruben se han asegurado de que acabara y me han hecho pasar buenos ratos, con unos buenos partidos y con frases como: "le vamos a decir a Edith que te quite el wifi" o "mucho ves tú Juego de Tronos".

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Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB

Cited by 19 publications

References 26 publications

Advances in the Pennsylvania State University NEM code

Advances in the Pennsylvania State University NEM code

Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis

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

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