tailieunhanh - 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 the EP, the PP and the AUU are capable of controlling the reactor power by adjusting the control rods during the accidents. | TẠP CHÍ KHOA HỌC ĐẠI HỌC ĐÀ LẠT Tập 7, Số 3, 2017 329–341 329 THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR Tran Dang Khoaa*, Trinh Thi Tu Anhb a The Faculty of Nuclear Science, National Tsing Hua University, Taiwan, China The Research Management and International Cooperation Department, Dalat University, Lamdong, Vietnam b Article history Received: November 18th, 2016 | Received in revised form: December 09th, 2016 Accepted: December 12th, 2016 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. Keywords: Feed water pump; Main circulation pump; Safety system; WWER-1000 nuclear reactor. 1. INTRODUCTION WWER is an abbreviation for Water Energy Reactor. It is a pressure vessel type nuclear reactor with water used both as moderator and coolant, resulting in a thermal neutron spectrum. The main distinguishing features of the WWER compared to other PWRs are horizontal steam generators and hexagonal fuel assemblies. The WWER-1000 (IAEA, 2011) core is composed of fuel assemblies (FA) having hexagonal formant located on a hexagonal grid with constant pitch of about 236 mm. Additionally, the steam generator (SG) is intended for heat removal from primary circuit coolant and forming saturated steam in the secondary circuit. Steam .