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Published: 2011-06-30
Abstract Views: 38
DOI: https://doi.org/10.53747/nst.v1i2.299
Issue
Vol. 1 No. 2 (2011)
Section
Articles
How to Cite
DUONG , N. H., & NGUYEN , T. T. (2011). THERMAL HYDRAULIC SYSTEM AND NUMERICAL MODELLING OF VVER-1000 NUCLEAR REACTOR IN VIEW OF THE 1ST NINH THUAN NUCLEAR POWER PLANT. Nuclear Science and Technology, 1(2), 15-26. https://doi.org/10.53747/nst.v1i2.299

THERMAL HYDRAULIC SYSTEM AND NUMERICAL MODELLING OF VVER-1000 NUCLEAR REACTOR IN VIEW OF THE 1ST NINH THUAN NUCLEAR POWER PLANT

DUONG NGOC HAI1,2, NGUYEN TAT THANG3,4
1 Institute of Mechanics, Vietnam Academy of Science and Technology (VAST), 264 Doi Can, Ba Dinh, Hanoi ,Vietnam.
2 University of Engineering and Technology, Vietnam National University of Hanoi (VNU), 144 Xuan Thuy, Hanoi, Vietnam,
3 Institute of Mechanics, Vietnam Academy of Science and Technology (VAST), 264 Doi Can, Ba Dinh, Hanoi ,Vietnam. 2)
4 Tokyo Institute of Technology (TITECH),2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550, Japan.

Main Article Content

Abstract

This paper presents an overview of the thermal-hydraulic system of Russian VVER-1000 pressurized water reactors (PWRs) and some results of our study on the numerical simulation using VISA_RELAP5 integrated code. This research has been carried out in view of the 1st nuclear power plant of Vietnam that will use VVER type reactors. It should be noted that knowledge of the VVER reactor system is still lacking in Vietnam now. The data that we used in our research is real data of the Kalinin nuclear power plant (NPP) in Russia. Therefore this research has important practical implications especially for the preparation for the safe operation and proper management of incidents (accidents) for the 1st NPP of Vietnam.

Article Details

Keywords

VVER-1000, Thermal hydraulic, VISA, RELAP5, PWR, Ninh Thuan NPP

References

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