THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR

Authors

  • Trần Đăng Khoa The Faculty of Nuclear Science, National Tsing Hua University, Taiwan, China
  • Trịnh Thị Tú Anh The Research Management and International Cooperation Department, Dalat University, Viet Nam

DOI:

https://doi.org/10.37569/DalatUniversity.7.3.336(2017)

Keywords:

Feed water pump, Main circulation pump, Safety system, WWER-1000 nuclear reactor.

Abstract

In this study, the operation and response capability of safety system in nuclear reactor WWER-1000 was analyzed during the accidents that involved the failure of main circulation pump or feed water pumps. The nuclear reactor WWER-1000 simulator developed by IAEA showed that safety systems such as the EP, the PP and the AUU are capable of controlling the reactor power by adjusting the control rods during the accidents. Also, the ACP allowed the nuclear reactor to operate safely at 65%, 61 % and 39% power for the wheel jam of MCP-1, the trip of MCP-1 and the FWP-1 accident, respectively. Additionally, the water in steam generator remained at the original value (224 mm) by SG water level controller to ensure the heat exchange within the reactor.

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References

Andrushenko, X. A., Aphrov, A. M., Vaciliev, B. I., Genheralov, V. N., Koxounov, K. B., Shemchenkov, I. M., & Ukraixev, V. P. (2012). Nhà máy điện hạt nhân sử dụng lò phản ứng WWER-1000. Hà Nội, Việt Nam: NXB Khoa học và Kỹ thuật.

IAEA (2011). WWER-1000 Reactor manual (3rd ed.). Retrieved from https:// www.iaea.org/NuclearPower/Downloads/Simulators/WWER-1000-Simulator-Manual-2011.10.pdf.

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Published

15-09-2017

Volume and Issues

Section

Natural Sciences and Technology

How to Cite

Khoa, T. Đăng, & Anh, T. T. T. (2017). THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR. Dalat University Journal of Science, 7(3), 329-341. https://doi.org/10.37569/DalatUniversity.7.3.336(2017)