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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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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spelling oai:scholar.dlu.edu.vn:DLU123456789-1142522023-10-27T14:44:05Z THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR Trần, Đăng Khoa Trịnh, Thị Tú Anh 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. 2023-03-04T08:23:18Z 2023-03-04T08:23:18Z 2017 Article 0866-787X https://tckh.dlu.edu.vn/index.php/tckhdhdl/article/view/336 https://scholar.dlu.edu.vn/thuvienso/handle/DLU123456789/114252 10.37569/DalatUniversity.7.3.336(2017) en Tạp chí Khoa học Đại học Đà Lạt, Tập 7, Số 3; tr. 329-341 application/pdf Trường Đại học Đà Lạt
institution Thư viện Trường Đại học Đà Lạt
collection Thư viện số
language English
description 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.
format Article
author Trần, Đăng Khoa
Trịnh, Thị Tú Anh
spellingShingle Trần, Đăng Khoa
Trịnh, Thị Tú Anh
THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR
author_facet Trần, Đăng Khoa
Trịnh, Thị Tú Anh
author_sort Trần, Đăng Khoa
title THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR
title_short THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR
title_full THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR
title_fullStr THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR
title_full_unstemmed THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR
title_sort assessment of safety systems in wwer-1000 nuclear reactor using iaea simulator
publisher Trường Đại học Đà Lạt
publishDate 2023
url https://tckh.dlu.edu.vn/index.php/tckhdhdl/article/view/336
https://scholar.dlu.edu.vn/thuvienso/handle/DLU123456789/114252
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