Effect of modelling cross-flow on the simulation of SBLOCA experiments of PSB-VVER test facility
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Date
2019-12
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Publisher
Turkish Atomic Energy Authority
Abstract
Bu çalışmada, PSB-VVER test tesisinde küçük kırıklı soğutucu kaybı kazası (KKSKK) modellenmiştir. OECD PSB-VVER projesi kapsamında hazırlanmış olan bir RELAP5 kodu girdi dosyası kullanılarak, termal-hidrolik kanallar arasında çapraz akış modellenmiştir. Çapraz akışın modellenmesi sonucunda akışın karıştığı gerçekçi durumlar için simülasyon sonuçları incelenmiştir. Bu simülasyon sonuçları, akışın karışmadığı durumla kıyaslanmış ve maksimum yakıt sıcaklığı, akümülatör ve düşük basınç soğutma sistemi devreye giriş zamanı, kütlesel akış hızı parametrelerinin çapraz akıştan nasıl etkilendiği gözlemlenmiştir. Kor nodalizasyonunda
yapılan değişiklikler ve hesaplar RELAP5 MOD 3.5 veri dosyasına işlenerek elde edilen sonuçlar PSB-VVER tesisi deneysel sonuçları ile kıyaslanarak kod doğrulaması yapılmıştır.
In this work, small break loss of coolant accident (SBLOCA) was modelled at PSBVVER test facility. By using a RELAP5 input deck prepared during OECD PSB-VVER project, cross-flow flow between the thermalhydraulic channels is modeled. As the result of modelling lateral flow, the results of simulations were investigated for the realistic situations where the flow is mixed. The results of simulations were compared with the results obtained by simulating the cases where flow mixing was not modeled and effect of modelling cross-flow on the calculation of peak clad temperature, actuation time of the accumulator and the low pressure emergency core cooling system in addition to mass flow rate was observed. Code validation was performed by comparing PSB-VVER test facility experimental results with the simulation results obtained by changing the core nodalization in RELAP5 MOD 3.5 input file for crossflow modelling.
In this work, small break loss of coolant accident (SBLOCA) was modelled at PSBVVER test facility. By using a RELAP5 input deck prepared during OECD PSB-VVER project, cross-flow flow between the thermalhydraulic channels is modeled. As the result of modelling lateral flow, the results of simulations were investigated for the realistic situations where the flow is mixed. The results of simulations were compared with the results obtained by simulating the cases where flow mixing was not modeled and effect of modelling cross-flow on the calculation of peak clad temperature, actuation time of the accumulator and the low pressure emergency core cooling system in addition to mass flow rate was observed. Code validation was performed by comparing PSB-VVER test facility experimental results with the simulation results obtained by changing the core nodalization in RELAP5 MOD 3.5 input file for crossflow modelling.
Description
Keywords
Loss of coolant accident, Soğutucu kaybı kazası, Small break, Küçük kırık, Thermal-hydraulic analysis, Termal-hidrolik analiz, Code validation, Kod doğrulama, PSB-VVER, VVER, RELAP5
Citation
Türkal, T. ve Ergün, Ş. (2019). Effect of modelling cross-flow on the simulation of SBLOCA experiments of PSB-VVER test facility. Turkish Journal of Nuclear Sciences, 31(2), 105-117.