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

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 th...

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Chi tiết về thư mục
Những tác giả chính: Trần, Đăng Khoa, Trịnh, Thị Tú Anh
Định dạng: Bài viết
Ngôn ngữ:English
Được phát hành: Trường Đại học Đà Lạt 2023
Truy cập trực tuyến:https://tckh.dlu.edu.vn/index.php/tckhdhdl/article/view/336
https://scholar.dlu.edu.vn/thuvienso/handle/DLU123456789/114252
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Thư viện lưu trữ: Thư viện Trường Đại học Đà Lạt
Miêu tả
Tóm tắt: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.