Qualification of Coupled 3-D Neutron-Kinetic/Thermal-Hydraulic Code Systems by the Calculation of Main-Steam-Line-Break Benchmarks in an NPP with VVER-440 Reactor

Kliem, S.; Danilin, Sergey; Hämäläinen, Anitta; Hadek, J.; Keresztúri, A.; Siltanen, P.

doi:10.13182/nse07-a2728

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Coupling Of Dyn3d and Flica4 Or Flocal1

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Cited by 17 publications

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“…The DYN3D code has already been coupled to the CFD code ANSYS CFX (Kliem et al, 2011b) and to the thermal-hydraulics system codes ATHLET and RELAP5 (Kliem et al, 2007;Grundmann and Kliem, 2003). The experience obtained in these activities was used to conduct the coupling with FLICA4 in an efficient way.…”

Section: Coupling Of Dyn3d and Flica4 Or Flocalmentioning

confidence: 99%

Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project

Varas

Herrero

Gommlich

et al. 2015

Annals of Nuclear Energy

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Section: Coupling Of Dyn3d and Flica4 Or Flocalmentioning

confidence: 99%

Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project

Varas

Herrero

Gommlich

et al. 2015

Annals of Nuclear Energy

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“…The hot zero power MSLB analyses using the STAR and the RETRAN codes reported in (Feltus, 1994) were one of the earliest works in that area. The first international benchmarks for coupled code systems were based on postulated MSLB accidents, the TMI-1 benchmark (Ivanov et al, 2003) for a reactor core with rectangular fuel assembly cross section and the WER-440 benchmark (Kliem et al, 2007) for hexagonal fuel assemblies.…”

Section: Introductionmentioning

confidence: 99%

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

Kliem

Kozmenkov

Hadek

et al. 2017

Nuclear Engineering and Design

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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.

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