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Journal articles on the topic 'VVER-1200'

Author: Grafiati

Published: 28 June 2021

Last updated: 7 February 2022

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1

Tran, Vinh Thanh, Viet Phu Tran, and Thi Dung Nguyen. "A study on the core loading pattern of the VVER-1200/V491." Nuclear Science and Technology 7, no. 1 (September 1, 2021): 21–27. http://dx.doi.org/10.53747/jnst.v7i1.115.

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The VVER-1200/V491 was a selected candidate for the Ninh Thuan I Nuclear Power Plant.However, in the Feasibility Study Safety Analysis Report (FS-SAR) of the VVER-1200/V491, the core loading pattern of this reactor was not provided. To assess the safety features of the VVER- 1200/V491, finding the core loading patterns and verifying their safety characteristics are necessary. In this study, two core loading patterns of the VVER-1200/V491 were suggested. The first loading pattern was applied from the VVER-1000/V446 and the second was searched by core loading optimization program LPO-V. The calculations for power distribution, the effective multiplication factor (k-eff), and fuel burn-up were then calculated by SRAC code. To verify several safety parameters of loading patterns of the VVER-1200/V491, the neutron delayed fraction (DNF), fuel andmoderator temperature feedbacks (FTC and MTC) were investigated and compared with the safety standards in the VVER-1200/V491 FS-SAR or the VVER-1000/V392 ISAR.

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2

Le, Dai Dien. "Comparative analysis of reactor coolant pump coastdown transient using VVER-1200 NPP simulator." Nuclear Science and Technology 7, no. 1 (September 1, 2021): 10–20. http://dx.doi.org/10.53747/jnst.v7i1.114.

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Verification has been performed to check the VVER-1200 NPP simulator installed atNuclear training Center, VINATOM by comparing main parameters in nominal power operation with design data given in safety analysis report of VVER-1200/V392M as well as Ninh Thuan FSSAR. A good agreement was found between the VVER-1200 NPP simulator and VVER-1200/V392M. In this study, the reactor coolant coastdown transient is investigated using the VVER-1200 NPP simulator in comparison with SAR documents. The real time feature of the simulator as well as simulated results performed in the simulator through switching off one reactor coolant pump in comparison with VVER-1000 experiments are given. A good agreement between the measured and simulated results shows that the thermal hydraulic characteristics and the control protection systems are modeled in a reasonable way. The analysis gives a good basis for the further studies on the simulator.

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3

Aver’yanova, S. P., and P. E. Filimonov. "Xenon stability of VVER-1200." Atomic Energy 107, no. 6 (December 2009): 424–28. http://dx.doi.org/10.1007/s10512-010-9246-7.

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4

Bui, Thi Hoa, Tan Hung Hoang, and Minh Giang Hoang. "Safety Analyses of VVER-1200/V491 reactor for longterm station blackout along with small LOCAs." Nuclear Science and Technology 6, no. 4 (December 30, 2016): 8–17. http://dx.doi.org/10.53747/jnst.v6i4.171.

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Performance of Passive Heat Removal through Steam Generator (PHRS-SG) of VVER-1200/V491 reactor presented in Safety Analysis Report for Ninh Thuan 1 shows that in case of long term station black out (SBO), VVER-1200/V491 reactor can be cooldown and remained in safety mode at least 24 hours based on PHRS-SG performance. Anyway, long term station blackout along with small break in main coolant pipe of VVER-1200/V491 is assumed to be happening as an extension design condition that needs to be investigated. This study focuses on investigation of SBO along with different size of small break of LOCAs with expectation of finding the range of break size that the reactor is still kept in safety mode during 24 hours. During the investigation, some indicators for fuel damage such as the timing of HA1 actuation or mass of coolant inventory discharged are introduced as necessary information contributed to Severe Accident Management Guideline (SAMG).

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5

Arzhaev, Alexander, Alexey Arzhaev, Valentin Makhanev, Mikhail Antonov, Anton Emelianov, Aleksander Kalyutik, Yury Karyakin, et al. "Possible in-service damages of steam generators at VVER-1000 and VVER-1200 NPP units and their impact on long-term operation." E3S Web of Conferences 209 (2020): 03005. http://dx.doi.org/10.1051/e3sconf/202020903005.

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Specific features of corrosion-mechanical damages of primary circuit header to steam generator vessel branch welds at VVER-1000 NPPs and their impact on safety and economic efficiency during long-term operation are analysed. Measures to avoid the damages for similar zones of VVER-1200 steam generators are discussed.

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6

Al Malkawi, Rashdan Talal, Sergey B. Vygovsky, and Osama Wasef Batayneh. "Investigation of the impact of steady-state VVER-1000 (1200) core characteristics on the reactor stability with respect to xenon oscillations." Nuclear Energy and Technology 6, no. 4 (November 20, 2020): 289–94. http://dx.doi.org/10.3897/nucet.6.60464.

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The article presents a method for obtaining an analytical expression for the criterion of stability of a VVER-1000 (1200) reactor with respect to xenon oscillations of the local power in the core, containing an explicit dependence of the criterion ratio coefficients on the arbitrary axial neutron field distribution in steady states of the core. Based on the data of numerical experiments using a full-scale model of the Kalinin NPP power units, the authors present the results of checking the validity of this expression for the reactor stability criterion with respect to xenon oscillations for different NPPs with VVER-1000 (1200) reactors.

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7

Gusev, Igor Nikolaevich, Vladimir Ruslanovich Kazanskiy, and Igor Leonidovich Vitkovsky,. "Dynamic stability of the VVER-1200 power unit." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2017, no. 3 (October 2017): 22–32. http://dx.doi.org/10.26583/npe.2017.3.02.

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8

Gusev, I. N., V. R. Kazanskiy, and I. L. Vitkovsky. "Dynamic stability of the VVER-1200 power unit." Nuclear Energy and Technology 3, no. 4 (December 2017): 270–77. http://dx.doi.org/10.1016/j.nucet.2017.10.004.

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9

Kovács, Dorina, and Dávid Kemény. "Investigation of VVER-1200 reactor pressure vessel’s material." IOP Conference Series: Materials Science and Engineering 903 (August 26, 2020): 012051. http://dx.doi.org/10.1088/1757-899x/903/1/012051.

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10

Petrovski, A. M., T. N. Korbut, E. A. Rudak, and M. O. Kravchenko. "Accounting of the vver-1200 overload influence for fission products activities calculating." Proceedings of the National Academy of Sciences of Belarus, Physical-Technical Series 64, no. 4 (January 11, 2020): 491–96. http://dx.doi.org/10.29235/1561-8358-2019-64-4-491-496.

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Current work is aimed at the analysis of the fission products decay influence during fuel reloading, when calculating the accumulated fission products activity for the VVER-1200 reactor fuel campaign. The Bateman problem solution based technique was used for calculations, within the framework of the two fissile nuclides approximation. The fission products producing process for the VVER-1200 reactor stationary campaign is considered, taking into account the reactor shutdown periods for refueling and without taking them into account (instant reload approximation). It was shown, that the instant reload approximation for fission products activity calculations gives the similar accurate result, as calculations with taking into account the shutdown periods. The results can be used to significantly simplify the calculations of fission product activity accumulation in nuclear power reactors.

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11

Zvonarev, Yu A., D. F. Tsurikov, V. L. Kobzar, A. M. Volchek, N. P. Kiselev, V. F. Strizhov, A. S. Filippov, and E. V. Moiseenko. "Numerical analysis of core catcher efficiency for VVER-1200." Physics of Atomic Nuclei 74, no. 13 (December 2011): 1845–53. http://dx.doi.org/10.1134/s1063778811130084.

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12

Averianova, S. P., A. A. Dubov, K. B. Kosourov, Yu M. Semchenkov, and P. E. Filimonov. "VVER-1200/1300 operation in a daily load schedule." Atomic Energy 113, no. 5 (March 2013): 305–13. http://dx.doi.org/10.1007/s10512-013-9637-7.

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13

Hafez, Noura, Hesham Shahbunder, Esmat Amin, S. A. Elfiki, and A. Abdel-Latif. "Study on criticality and reactivity coefficients of VVER-1200 reactor." Progress in Nuclear Energy 131 (January 2021): 103594. http://dx.doi.org/10.1016/j.pnucene.2020.103594.

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14

Hashlamoun, Taha M., Sergey B. Vygovsky, Sergey T. Leskin, and A. Safa Duman. "Determination of 18-month fuel cycle parameters for the purpose of fuel costs minimization at the basis of use constructions of fuel assemblies in VVER-1200 reactors." Nuclear Energy and Technology 5, no. 1 (March 20, 2019): 9–15. http://dx.doi.org/10.3897/nucet.5.33976.

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This article presents the results of research, that were focused on determining the optimal parameters of the extension of (reactor life-time) reactor fuel cycle in order to reduce the total operating costs of nuclear power plants during the transition from 12-month reactor fuel cycle to 18-month fuel cycle. The relevance of the research is related to the fact that, in recent years, there is a transition at all operating nuclear power plants VVER-1000 (1200) from 12-month reactor fuel cycle to extended 18-month fuel cycle. At the same time, represent the interests to solve the problem of conservation the extension of reactor life-time while reducing the number of loaded fuel assemblies with fresh fuel assemblies, which would reduce the total operating, and fuel costs. Search for solutions of this problem is associated with mandatory implementation of all requirements for the safe operation of the reactor and the reduction of the maximum fast neutron fluence on the reactor vessel in comparison with its value at the operating nuclear power plants. In the present work, with using the program PROSTOR software complex researched the neutron-physical characteristics of the core at the nominal parameters of the VVER-1200 reactor through the implementation of various fuel cycle strategies. The article developed various schemes of fuel-reloading for an 18-month fuel cycle with a different number of fuel assemblies. The article carries out a comparative analysis of the main parameters in the core for fuel-reloading schemes options of an 18- and 12-month fuel cycle with each other. Determine the minimum amount of fuel assemblies and provide the necessary duration of the reactor life-time for 18-month fuel cycle with using the extension of reactor life-time by reducing the power at the end of the reactor cycle to 70% of the nominal power. In the article, the arrangements of fuel assemblies were developed to provide limitations of local power by volume of the core, which reduce the fluence of fast neutrons on the reactor vessel in comparison with the projected value of the fluence. This article shows that the 18-month fuel cycle for the VVER-1200 reactor is more economical than the 12-month fuel cycle. These studies were carried out for the VVER-1200 reactor at the power of 100% of the nominal.

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15

Asmolov, Vladimir Georgievich, Igor Nikolaevich Gusev, Vladimir Ruslanovich Kazanskiy, Vladimir Petrovich Povarov, and Dmitry Borisovich Statsura. "New generation first of the kind unit – VVER 1200 design features." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2017, no. 3 (October 2017): 5–21. http://dx.doi.org/10.26583/npe.2017.3.01.

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16

Shaat, Mohamed. "Advanced Technology and Safety Features of VVER-1200 Nuclear Power Plant." International Conference on Chemical and Environmental Engineering 9, no. 6 (April 1, 2018): 452. http://dx.doi.org/10.21608/iccee.2018.34697.

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17

Asmolov, V. G., I. N. Gusev, V. R. Kazanskiy, V. P. Povarov, and D. B. Statsura. "New generation first-of-the kind unit – VVER-1200 design features." Nuclear Energy and Technology 3, no. 4 (December 2017): 260–69. http://dx.doi.org/10.1016/j.nucet.2017.10.003.

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18

Panka, I., Gy Hegyi, A. Keresztúri, Cs Maráczy, and E. Temesvári. "Hot channel calculation methodologies in case of VVER-1000/1200 reactors." Kerntechnik 83, no. 4 (August 27, 2018): 365–75. http://dx.doi.org/10.3139/124.110899.

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19

Fejt, F., M. Sevecek, J. Frybort, and O. Novak. "Study on neutronics of VVER-1200 with accident tolerant fuel cladding." Annals of Nuclear Energy 124 (February 2019): 579–91. http://dx.doi.org/10.1016/j.anucene.2018.10.040.

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20

Vorobyov, Yu, O. Zhabin, and M. Frankova. "Application of RELAP5/MOD3.2 Cladding Deformation Model for VVER-1000 Fuel in Design-Basis Accident Analysis." Nuclear and Radiation Safety, no. 3(71) (August 15, 2016): 19–22. http://dx.doi.org/10.32918/nrs.2016.3(71).04.

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The paper presents applicability of built-in RELAP5/MOD3.2 cladding deformation model for VVER-1000 fuel with cladding of Zr+1 % Nb alloy. Experimental data and simplified model of fuel assembly channel of the core are used for this purpose. The model applicability is tested for the hot channel blockage after cladding swelling and rupture in the interval of temperatures from 600 to 1200°С and interval of pressures from 1 to 12 MPa. It is demonstrated that RELAP5/MOD3.2 builtin model of cladding deformation can be applied to VVER-1000 cladding of Zr+1%Nb alloy rupture estimation only in the certain limited range of parameters. The analysis of RELAP5/MOD3.2 cladding deformation model parameters influence on the peak cladding temperature in double-ended cold leg break was performed. The paper presents recommendations on the use of RELAP5/MOD3.2 built-in cladding deformation model in the design basis accident analysis of VVER-1000 reactors.

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21

Temesvári, E., Gy Hegyi, and Cs Maráczy. "Analysis of the startup physics tests of a VVER-1200 reactor with the KARATE-1200 code system." Kerntechnik 85, no. 4 (September 14, 2020): 250–56. http://dx.doi.org/10.3139/124.200010.

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22

Halász, M., and M. Szieberth. "Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors." Kerntechnik 83, no. 4 (August 27, 2018): 319–24. http://dx.doi.org/10.3139/124.110906.

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23

Hafez, Noura, Hesham Shahbunder, Esmat Amin, S. U. El-Kamessy, S. A. Elfiki, and Ahmed Latef. "The Effect of burnable absorbers on neutronic parameters of VVER-1200 reactor." IOP Conference Series: Materials Science and Engineering 956 (October 28, 2020): 012007. http://dx.doi.org/10.1088/1757-899x/956/1/012007.

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24

Aver’yanova, S. P., N. S. Vokhmyanina, D. A. Zlobin, P. E. Filimonov, and V. P. Povarov. "Investigation of Transient Xenon Processes in VVER-1200 at the Novovoronezh NPP." Atomic Energy 124, no. 4 (August 2018): 215–20. http://dx.doi.org/10.1007/s10512-018-0400-y.

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25

Pogorelov, Yegor, Nikolay Anosov, Vladimir Skorobogatykh, Lyubov Gordyuk, Vasiliy Mikheev, and Valentin Shamardin. "Brittle fracture resistance of reactor pressure vessel steels in the initial state." Nuclear Energy and Technology 4, no. 3 (December 7, 2018): 155–61. http://dx.doi.org/10.3897/nucet.4.30779.

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The authors investigate the influence of chemical and structural inhomogeneity on the brittle fracture resistance (BFR) of VVER vessel materials in the initial state (without irradiation). It is proposed to replace the brittle fracture resistance assessment using the critical brittleness temperature TC for the BFR assessment using the brittle-viscous transition temperature TT. Consideration was given to calibration charts used for studying the TT dependence on the grain size and heat treatment. A comparison of the TC and TT values in the experimental industrial 15H2NMFA-A steel billets shows that the TC values are significantly lower than the TT values: – at the lower level of conservatism, the difference between TC and TT is 22 °C; – at the upper level of conservatism, this difference is 24 °C. The array data on the critical brittleness temperature and the ductile-to-brittle transition temperature of impact test samples of 15H2NMFAA (for VVER-1000) and 15H2NMFA grade 1 (for VVER-1200) steels were statistically processed. The industrial shell samples were manufactured at the “Energomashspetsstal” plant (Kramatorsk, Ukraine). It was found that, in the metal of VVER-1000 vessel surveillance specimens with the copper content – less than 0.06%, heat treatment has a significant effect on the TT value, which changes from –99 to –28°C; – from 0.07 to 0.12%, heat treatment has a significant effect on the TT value, which changes from –60 to –40°C.

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26

Vygovsky, Sergey B., Fedor V. Gruzdov, and Rashdan T. Al Malkawi. "A study into the dependence of the cladding-fuel pellet gap conductance on burn-up and the effects on the reactor core neutronic performance." Nuclear Energy and Technology 5, no. 2 (May 17, 2019): 97–102. http://dx.doi.org/10.3897/nucet.5.35579.

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This paper presents the results of the research to study the dependence of the VVER-1000 (1200) cores neutronic characteristics on the cladding – fuel pellet gap conductance coefficient in the process of the fuel burn-up. The purpose of the study was to determine more accurately the dependence of the cladding – fuel pellet gap conductance coefficient on the fuel burn-up as shown in the Final Safety Report for the Bushehr NPP and to determine the extent of the effects this dependence had on the spatial distribution of the neutron field, on the xenon accumulation rate, and on the kinetic and dynamic behavior of the reactor facility. The paper presents the results of calculating the parameters using which the heat engineering safety of the reactor core is monitored in the process of the fuel burn- up (for a generalized fuel load of a VVER-1000) during the transition to an 18-month nuclear fuel cycle. This paper also includes the results of a numerical research to determine the cladding – fuel gap conductance coefficient depending on the fuel burn-up. These results have shown that, in reality, the gap conductance coefficient dependence on the burn-up does not affect greatly the steady-state characteristics. At the same time, it affects to rather a great extent the xenon accumulation rate, specifically in the event of an extended fuel life. In conditions of maneuvering (load following) modes accompanied by the xenon processes in the reactor core. These facts should be into consideration in design of engineering codes, that used to support the operation of the VVER-1000 (1200) and full-scale simulators.

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27

Baikov, A. V., A. A. Dubov, A. V. Kotsarev, and B. E. Shumskii. "Simulation of a Transient Process in VVER-1200 by Means of the Athlet/BIPR-VVER Coupled Neutronics and Thermohydraulic Code." Atomic Energy 127, no. 4 (January 30, 2020): 197–201. http://dx.doi.org/10.1007/s10512-020-00610-w.

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28

Khai, Nguyen Tuan, Le Dinh Cuong, Do Xuan Anh, Duong Duc Thang, Trinh Van Giap, Nguyen Thi Thu Ha, Vuong Thu Bac, and Nguyen Hao Quang. "Assessment of Radioactive Gaseous Effluent Released From Nuclear Power Plant Ninh Thuan 1 under Scenario of Ines-Level 5 Nuclear Accident." Communications in Physics 25, no. 2 (September 11, 2015): 165. http://dx.doi.org/10.15625/0868-3166/25/2/6133.

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Based on guides RG 1.109, RG 1.111 published by United States Nuclear Regulatory Commission (USNRC)~our~research~concentrates on assessing radiation doses caused by radioactive substances released from the nuclear power plant (NPP) Ninh Thuan 1 to the environment under scenario of an INES-level 5 nuclear accident caused by two incidents of the station black out (SBO) and loss of coolant accident (LOCA) using software~RASCAL4.3~provided by the Emergency Operations Center of USNRC. The plant Ninh Thuan 1 is assumed to use the VVER-1200 technology with a total power of 2400 MW\(_{e}\). The input data for the model calculations is based on building the accident scenario, the technical parameters of VVER-1200 technology and the meteorology. The meteorological data on dry and rainy seasons, which are typical for the Ninh Thuan region was also considered. The \(X/Q\) (s/m\(^{3}\)) quality and the maximum dose values were calculated within an area of 40 km radius from the NPP site, where \(X/Q\) (s/m\(^{3}\)) is the ratio of activity concentration to release rate. Based on the obtained results on dose distribution the necessary measures for nuclear emergency preparedness have been proposed according to the IAEA recommendations.

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29

Xu, Yubin. "Optimizing the Neutronic Parameters for VVER-1200 Reactor Core Using WIMS-ANLS Code." Global Nuclear Safety 13, no. 1 (March 2018): 87–95. http://dx.doi.org/10.26583/gns-2018-01-09.

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30

Petrovskiy, A. M., T. N. Korbut, E. A. Rudak, and M. O. Kravchenko. "Calculating the Neutron Radiation in the Spent Nuclear Fuel of VVER-1200 Reactors." Bulletin of the Russian Academy of Sciences: Physics 84, no. 10 (October 2020): 1295–99. http://dx.doi.org/10.3103/s1062873820100184.

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31

Averyanova, S. P., A. A. Dubov, K. B. Kosourov, Yu M. Semchenkov, and P. E. Filimonov. "Development of Methods for VVER-1200/1300 Control in a Daily Load Schedule." Atomic Energy 114, no. 5 (September 2013): 308–14. http://dx.doi.org/10.1007/s10512-013-9716-9.

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32

Afanasiev, D. A., Yu A. Kraynov, A. A. Pinegin, and S. V. Tsyganov. "Physical startup tests for VVER-1200 of Novovoronezh NPP: advanced technique and some results." Kerntechnik 82, no. 4 (September 2017): 365–71. http://dx.doi.org/10.3139/124.110817.

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33

Ferrer, R., J. Hykes, and J. Rhodes. "Development of CASMO5 for VVER-1000/1200 analysis and preliminary validation using critical experiments." Kerntechnik 84, no. 4 (September 16, 2019): 214–27. http://dx.doi.org/10.3139/124.190006.

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34

Kamenskaya, D. D., O. V. Tarasov, A. S. Filippov, and D. K. Valetov. "Radiative and Convective Heat Transfer in the Gas Cavity of VVER-1200 Melt Trap." Atomic Energy 125, no. 2 (November 24, 2018): 112–18. http://dx.doi.org/10.1007/s10512-018-0451-0.

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35

Vnukov, Ruslan Adhamovich, Valerij Vasil’evich Kolesov, Irina Andreevna Zhavoronkova, Yaroslav Aleksandrovich Kotov, and Masum Rana Pramanik. "Effect of the Burnable Absorber Arrangement on the VVER(1200 Fuel Assembly Neutronic Performance." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2021, no. 2 (June 2021): 27–37. http://dx.doi.org/10.26583/npe.2021.2.03.

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36

Vnukov, Ruslan A., Valery V. Kolesov, Irina A. Zhavoronkova, Yaroslav A. Kotov, and Md Masum Rana Pramanik. "Effect of the burnable absorber arrangement on the VVER-1200 fuel assembly neutronic performance." Nuclear Energy and Technology 7, no. 3 (September 23, 2021): 215–21. http://dx.doi.org/10.3897/nucet.7.73490.

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Optimizing the use of fuel in a power reactor is a task of current concern. However, little attention has been given to investigating the dependences among the enrichment used, the content of gadolinium oxide in fuel elements, and the life time in combination with assessing the efficiency of using Gd fuel elements with different Gd2O3 contents. The paper considers fuel assembly (FA) versions for VVER-1200 reactors having different enrichments for fuel elements, including those with Gd, and different contents of gadolinium oxide in fuel. A comparative analysis is presented for assemblies with homogeneous Gd2O3 arrangements in each fuel element and with profiled Gd2O3 arrangements. In the latter case, profiling depends on the neutron flux density in the layer which includes Gd fuel elements. This suggests that the arrangement of gadolinium oxide proportionally to the neutron flux density will improve the FA neutronic performance. The results were obtained using SERPENT (a continuous-energy multi-purpose three-dimensional Monte Carlo particle transport code). The assemblies with the used parameters for a 12-month fuel cycle have shown the method under consideration to be inefficient for a period of over 300 eff. days. With increased enrichment and content of gadolinium oxide, the use of profiled versions has turned out to be more rational for longer periods (up to 900 eff. days). Therefore, this phenomenon is relevant for the reactor life, whereas it proves to be insignificant for the fuel life. A complex relationship is noted between the gadolinium and uranium content in an assembly and the effective multiplication factor for the profiled and standard assemblies. This relationship requires further detailed consideration.

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37

Tunc, Murat, Ayse Nur Esen, Doruk Sen, and Ahmet Karakas. "Theoretical Post-Dryout Heat Transfer Model." International Journal of Computational Physics Series 1, no. 1 (March 1, 2018): 142–50. http://dx.doi.org/10.29167/a1i1p142-150.

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A theoretical post-dryout heat transfer model is developed for two-phase dispersed flow, one-dimensional vertical pipe in a post-CHF regime. Because of the presence of average droplet diameter lower bound in a two-phase sparse flow. Droplet diameter is also calculated. Obtained results are compared with experimental values. Experimental data is used two-phase flow steam-water in VVER-1200, reactor coolant system, reactor operating pressure is 16.2 MPa. On heater rod surface, dryout was detected as a result of jumping increase of the heater rod surface temperature. Results obtained display lower droplet dimensions than the experimentally obtained values.

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38

Bikeev, A. S., E. V. Bogdanova, E. K. Kosourov, D. A. Shkarovsky, and M. A. Kalugin. "Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code." Kerntechnik 83, no. 4 (August 27, 2018): 299–306. http://dx.doi.org/10.3139/124.110863.

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39

Saha, Arnob, Nashiyat Fyza, Altab Hossain, and M. A. Rashid Sarkar. "Simulation of tube rupture in steam generator and transient analysis of VVER-1200 using PCTRAN." Energy Procedia 160 (February 2019): 162–69. http://dx.doi.org/10.1016/j.egypro.2019.02.132.

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40

Nushtaeva, V. E., S. I. Spiridonov, R. A. Mikailova, E. I. Karpenko, S. N. Nushtaev, and A. S. Nygymanova. "Radiation Dose Assessment for Representative Biota Organisms in the Locale of NPP with VVER-1200." Atomic Energy 128, no. 4 (August 2020): 251–58. http://dx.doi.org/10.1007/s10512-020-00684-6.

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Dwiddar, Mohammed S., Alya A. Badawi, Hanaa H. Abou-Gabal, and Ibrahim A. El-Osery. "Investigation of different scenarios of thorium–uranium fuel distribution in the VVER-1200 first core." Annals of Nuclear Energy 85 (November 2015): 605–12. http://dx.doi.org/10.1016/j.anucene.2015.06.015.

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Galahom, A. Abdelghafar. "Reducing the plutonium stockpile around the world using a new design of VVER-1200 assembly." Annals of Nuclear Energy 119 (September 2018): 279–86. http://dx.doi.org/10.1016/j.anucene.2018.05.022.

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BULUT ACAR, Banu. "VVER-1200 Tipi Nükleer Reaktörün Kullanılmış Yakıtları İçin Depolama Tesisi Modeli Geliştirilmesi ve Maliyet Analizi." Afyon Kocatepe University Journal of Sciences and Engineering 20, no. 2 (May 20, 2020): 362–73. http://dx.doi.org/10.35414/akufemubid.605394.

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Egorov, Mikhail Yu. "Vertical steam generators for VVER NPPs." Nuclear Energy and Technology 5, no. 1 (March 20, 2019): 31–38. http://dx.doi.org/10.3897/nucet.5.33980.

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Steam generators for NPPs are the important large-sized metal consuming equipment of nuclear power installations. Efficiency of steam generator operation determines the overall service life of the whole nuclear facility. The main aim of the current study is to analyze advantages and shortcomings of horizontal and vertical types of steam generator design. This analysis is aimed at the development of recommendations for designing advanced steam generators for future Russian units of NPPs with VVER reactors of increased power. Design solutions and fifty-year experience of operation of 400 steam generators of horizontal type accepted in Russia and of vertical type applied by Westinghouse, Combustion Engineering, Siemens, Mitsubishi, Doosan were analyzed within the framework of the present study. Advantages and drawbacks of both types of equipment determining the development of conditions of the operating processes were also identified and systematized. Currently NPPs equipped with VVER are characterized with extended surface area of containment shells due to the application of four-loop design configuration and horizontal-type steam generators. It was established that steam generator equipment of horizontal type is characterized by such inherent disadvantages of design, technological and operational nature as the following: 1) small height and volume of the vapor space above the evaporation surface reducing separation capabilities and the capacity of the equipment as a whole; 2) impossibility of organizing separate single-phase pre-boiling section. Because of the above, horizontal steam generators with dimensions permissible for railroad transportation and, for VVER-1200 with reactor vessel diameter equal to 5 m, by water transport as well, have exhausted the possibilities for further significant increase of the per unit electric power. The demonstrated advantages of vertical-type steam generators were as follows: 1) absence of stagnant zones within the second cooling circuit, and, consequently, of hold-ups in them; 2) uniformity of heat absorption efficiency of the heating surface ensuring, as well, improved conditions for moisture separation; 3) high degree of moisture removal from steam-water mixture due to the combination of moisture separating elements of chevron and swirl-vane types; 4) increased temperature drop with parameters of generated steam elevated by 0.3 – 0.4 MPa. Conclusion was made on the advisability of introduction of steam generators with vertical-type layout in the Russian nuclear power generation. Practical tasks that need to be addressed in order to ensure introduction of vertical steam generators at NPPs with high-power VVER reactors were formulated.

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Khai, Nguyen Tuan, and Le Dinh Cuong. "Assessment of Radioactive Gaseous Effluent Released from Ninh Thuan 1 Nuclear Power Plant under Scenario of INES-level 7 Nuclear Accident." Communications in Physics 25, no. 4 (April 5, 2016): 375. http://dx.doi.org/10.15625/0868-3166/25/4/7671.

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Based on guidance RG 1.109, RG 1.111 published by United States Nuclear Regulatory Commission (USNRC) our research concentrates on assessing radiation doses caused by radioactive substances released from the Ninh Thuan 1 nuclear power plant (NPP) to the environment under scenario of an INES-level 7 nuclear accident caused by two incidents: Station Black Out (SBO) and Loss of Coolant Accident (LOCA) using software RASCAL4.3 provided by the Emergency Operations Center of USNRC. The NPP Ninh Thuan 1 is assumed to use the VVER-1200 technology with a total power of 2400 MWe from two units. The input data for the model calculations is built based on the accident scenario, the technical parameters of VVER-1200 technology and the meteorology. In this work the meteorological data on dry and rainy seasons which are typical for the Ninh Thuan region was considered. The maximum dose distributions were calculated within 40 km from the NPP site. The distributions are strongly affected by meteorological conditions. In the rainy season the dose values near the plant are higher than those in the dry season due to deposition effect of the radioactive substances. The calculation results show that consequences of the accident are very serious. A total radioactivity of radiological equivalence 225,000 TBq to 131I released to the atmosphere. Within 20km the Total Effective Dose Equivalence (TEDE) values are very high, about several tens of times greater than the dose limit. It is requested to establish National Steering Board for Accident Response to direct the relevant authorities in response for the accident consequences and ensure for security in the area of NPP. The public communication, emergency preparedness plan, people evacuation must be implemented under the guidance of Circular 25/2014/TT-BKHCN

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Dolganov, K., V. Semenov, A. Kiselev, D. Tomashchik, A. Fokin, V. Astakhov, A. Nikolaeva, et al. "Method for evaluation of loads on VVER‑1200 reactor pressure vessel from in-vessel steam explosions." Известия Российской академии наук. Энергетика, no. 5 (October 2018): 42–58. http://dx.doi.org/10.31857/s000233100003214-9.

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Dien, Le Dai, and Do Ngoc Diep. "Verification of VVER-1200 NPP Simulator in Normal Operation and Reactor Coolant Pump Coast-Down Transient." World Journal of Engineering and Technology 05, no. 03 (2017): 507–19. http://dx.doi.org/10.4236/wjet.2017.53043.

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Bezlepkin, V. V., M. A. Zatevakhin, O. P. Krektunov, Yu V. Krylov, O. V. Maslennikova, S. E. Semashko, R. A. Sharapov, V. K. Efimov, and Yu A. Migrov. "Computational and Experimental Validation of a Passive Heat Removal System for NPP Containment with VVER-1200." Atomic Energy 115, no. 4 (February 2014): 215–23. http://dx.doi.org/10.1007/s10512-014-9774-7.

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Mikailova, R. A., V. E. Nushtaeva, S. I. Spiridonov, E. I. Karpenko, and V. V. Krechetnikov. "Estimation and Prediction of the Population Irradiation Dose in the Vicinity of NPP with VVER-1200." Atomic Energy 127, no. 1 (November 2019): 56–59. http://dx.doi.org/10.1007/s10512-019-00584-4.

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Baranova, Yuliya Alekseevna, and Michael Timofeevich Slepov. "NPP-2006 with VVER-1200 type reactor – a new approach to displaying information from technical diagnostics systems." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2014, no. 4 (December 2014): 11–20. http://dx.doi.org/10.26583/npe.2014.4.02.

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