Analysis of the thermal-hydraulic parameters of VVER-1200 due to loss of coolant accident concurrent with loss of offsite power

Fyza, Nashiyat; Hossain, Altab; Sarkar, Rashid

doi:10.1016/j.egypro.2019.02.131

Cited by 11 publications

(6 citation statements)

References 5 publications

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“…Normal çalışma koşulunda, birincil soğutma suyu reaktöre ortalama 298 °C sıcaklıkla girmekte ve reaktörden ortalama 329 °C sıcaklıkla çıkmaktadır. Reaktör çekirdeğindeki ortalama yakıt sıcaklığı ise 800 °C'dir [76].…”

Section: şEkil 1 Vver-1200 çEkirdek Geometrisinin Radyal Görüntüsü [69]unclassified

Study on the Structure and Operation of the VVER-1200 Reactor and Cooling System

Özden¹,

Aközcan²

2022

JCHAR

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Son yıllarda ülkelerin hızlı sanayileşmesine ve dünya nüfusunun hızla artmasına paralel olarak artan enerji ihtiyacı her geçen gün daha da büyük bir sorun haline gelmiştir. Ülkeler bu ihtiyaçları karşılamak için farklı enerji kaynakları kullanmaya yönelmişlerdir. Nükleer enerji ve kullanımı birçok araştırmaya konu olmuştur. Nükleer santral, bir veya daha fazla sayıda nükleer reaktörün yakıt olarak radyoaktif maddeleri kullanarak ısı enerjisi bu enerjiden de elektrik enerjisinin üretildiği tesistir. VVER, ısı transferi ve moderatör olarak suyu kullanan dünyadaki en yaygın tip reaktörlerden biridir. VVER, esas olarak Rusya'da geliştirilen bir çeşit basınçlı su reaktörü (PWR) tasarımıdır. Sonuç olarak, mevcut çalışmanın amacı, VVER-1200 reaktörünü tüm yönleriyle anlatmak ve analiz etmektir.

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Section: şEkil 1 Vver-1200 çEkirdek Geometrisinin Radyal Görüntüsü [69]unclassified

Study on the Structure and Operation of the VVER-1200 Reactor and Cooling System

Özden¹,

Aközcan²

2022

JCHAR

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“…The lower head integrity of the RPV for the VVER-1200 (V-491) reactor is assessed in a study conducted by [18] using MELCOR 1.8.6 considering LB LOCAs and SBO occur at the same time. Moreover, [9] analyzed the thermal hydraulic parameters of the VVER-1200 reactor during LBLOCA concurrent with LOOP using PCTRAN. LOCA is the loss of coolant from the reactor due to a rupture in the main coolant pipeline.…”

Section: Introductionmentioning

confidence: 99%

Transient Analysis of LBLOCA with Subsequent Loss of Offsite Power and Loss of All AC Power in VVER-1200 Reactor

Asaduzzaman,

Hassan,

Hossain

et al. 2024

IOP Conf. Ser.: Mater. Sci. Eng.

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The generation III+ VVER-1200 (AES-2006) reactor is equipped with improved safety features with component redundancy compared to the previous models. This paper is concerned with the performance of active and passive safety features during the transient of a major beyond design basis accident (BDBA) scenario of the reactor. The study is done considering large break loss of coolant accident (LB LOCA) with loss of offsite power (LOOP) and LB LOCA with loss of all AC power (LOACP) sources namely station blackout (SBO) using VVER-1200 NPP simulator. It was found that the reactor is capable of mitigating such BDBA scenarios by the effectiveness of the active and passive safety systems. Moreover, LB LOCA with LOACP is observed to be more severe compared to LBLOCA with LOOP. This comparative analysis is compatible with IAEA safety guidelines.

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“…2-Using the simulator personal computer transient analyzer VVAR −1200 (PCTRAN VVER-1200), the parameter estimation, the validation, and the verifications of the developed model were carried out (Bezrukov et al, 2016;Fyza et al, 2019;Ibrahim et al, 2013;Khan & Islam, 2019;Mollah, 2018).…”

Section: Introductionmentioning

confidence: 99%

A developed analytical model for the pressurizer unit in nuclear power plants

Sheta

Ali

Fikry

et al. 2021

Journal of Radiation Research and Applied Sciences

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The pressure control in the pressurized water reactor (PWR) primary loop is key to secure the safe operation. The pressurizer (PZR) unit is responsible for attaining this task. Thus, the PZR unit's modeling is an important issue for the tracking control purpose and performance analysis concerning the turbine load. This paper develops a mathematical model to accurately predict the PZR unit pressure in the normal and load power changes. The model is a nonequilibrium three region model developed based on the thermodynamics of mass and energy for the water and steam in the PZR. The variations of the pressure and the temperature due to thermodynamic variables (enthalpy, density) and the mechanical work effect are considered in the developed model. The model also addresses other thermodynamic processes such as bulk flashing, spray condensation, interface condensation, wall condensation, and rainout flow. The inlet and outlet flow rates of the primary circuit (PC) and the average temperature and the hot leg temperature are included in the developed model. Based on data generated from the VVER-1200 simulator, parameter estimation, verification, and validation of the developed model through load power changes are achieved. Besides, a comparison with other models given in literature has been performed. This comparison indicated that the developed model is more sensitive against the minimum variation of PZR dynamics. Finally, a closed-loop PZR pressure control system, including a conventional Proportional Integral Derivative (PID) controller, was designed to test the control purpose's developed model. The simulation results over typical load change transients have been demonstrated the feasibility, effectiveness, and accuracy of the developed nonlinear model of PZR for dynamic modeling and control purposes.

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Analysis of the thermal-hydraulic parameters of VVER-1200 due to loss of coolant accident concurrent with loss of offsite power

Cited by 11 publications

References 5 publications

Study on the Structure and Operation of the VVER-1200 Reactor and Cooling System

Study on the Structure and Operation of the VVER-1200 Reactor and Cooling System

Transient Analysis of LBLOCA with Subsequent Loss of Offsite Power and Loss of All AC Power in VVER-1200 Reactor

A developed analytical model for the pressurizer unit in nuclear power plants

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