公开(公告)号：EP4257878A1

公开(公告)日：2023-10-11

申请号：EP21908731.9

申请日：2021-09-30

申请人： China Nuclear Power Technology Research Institute Co., Ltd. ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd.

发明人： ZHU, Jianmin ,  CHEN, Tianming ,  WANG, Na ,  HU, Yousen ,  ZHANG, Wei ,  LU, Xianghui ,  ZHOU, Mingjia ,  WANG, Kai ,  WANG, Xiaoting ,  WANG, Weiru ,  WEI, Danjing ,  LI, Bingwen ,  LIU, Yiran ,  HU, Yisong ,  GAO, Yaxin

IPC分类号： F22B1/02 ,  F22B35/00 ,  F22B37/42

摘要： Disclosed are a steam generator system, a steam generator pressure control system, and a control method therefor. The steam generator pressure control system comprises a first control module for obtaining a pressure deviation value; a second control module for measuring and calculating a flow difference value between an outlet flow value and an inlet flow value, and then adding the flow difference value and the pressure deviation value together to obtain a first opening degree value for controlling a first valve of a water supply regulation valve group; and a third control module for measuring a steam intake pressure value of a steam turbine, and comparing the steam intake pressure value with a preset reference threshold value, so as to obtain a second opening degree value for controlling a second valve of the water supply regulation valve group. In the steam generator system, the steam generator pressure control system, and the control method therefor of the present invention, the opening and closing conditions of the water supply regulation valve group is controlled by means of a first control module, a second control module and a third control module, such that a steam generator is controlled, thereby satisfying the requirements for both coarse regulation and fine regulation.

公开(公告)号：EP4216234A1

公开(公告)日：2023-07-26

申请号：EP20953572.3

申请日：2020-09-16

申请人： China Nuclear Power Technology Research Institute Co., Ltd. ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd.

发明人： WANG, Xinxin ,  DUAN, Rong ,  GAO, Wei ,  PAN, Hui ,  CAI, Dechang ,  LU, Xianghui ,  RUI, Min ,  YU, Chao ,  HE, Mingtao

IPC分类号： G21C3/328 ,  G21C7/06

摘要： The present invention relates to a small nuclear power reactor core and a ship. In the small nuclear power reactor core, twenty-one control rods include four power compensation rods A, five reactivity adjustment rods B, four temperature adjustment rods R, and eight shutdown rods S. The power of the reactor core is adjusted by adjusting the insertion depth of the power compensation rods A; the changes in reactivity of the reactor core caused by fuel burn-up and changes in xenon concentration are compensated for by adjusting the insertion depth of the reactivity adjustment rods B; the average temperature of the reactor core is adjusted by adjusting the insertion depth of the temperature adjustment rods R; the shutdown rods S provides additional negative reactivity to ensure a sufficient shutdown depth during shutdown of the reactor core. The control rods are functionally grouped and their layout is designed such that no soluble boron is required. These functional control rods are respectively used to control the power, temperature, shutdown of the reactor core, and compensate for the changes in reactivity of the reactor core caused by fuel burn-up and changes in xenon concentration, thereby realizing the miniaturization of nuclear power plant cores.

公开(公告)号：EP4421825A1

公开(公告)日：2024-08-28

申请号：EP22884863.6

申请日：2022-01-05

申请人： China Nuclear Power Technology Research Institute Co., Ltd ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd.

发明人： LIANG, Huo ,  LIU, Jinlin ,  YANG, Jiang ,  CHEN, Yunyin ,  CUI, Xuyang ,  LIU, Zhonghao ,  CHEN, Yichen ,  JI, Wenying ,  SHEN, Yonggang ,  OUYANG, Yong ,  LU, Xianghui ,  WANG, Xianmao ,  LIU, Jianchang

IPC分类号： G21C15/18

CPC分类号： Y02E30/30

摘要： A pressure suppression pool apparatus and a nuclear reactor. The pressure suppression pool apparatus comprises a housing (1) and at least one hollow pressure suppression pipe (2); a closed cavity and a plurality of baffles (3) for slowing gas flow are provided in the housing (1); the cavity is filled with a cooling liquid (11); the baffles (3) are submerged in the cooling liquid (11); an accommodating space (12) for accommodating gas is provided on the cooling liquid (11) inside the cavity; the pressure suppression pipe (2) passes through the outer wall of the housing (1), and comprises an out-of-housing section (21) located outside the housing (1) and an in-housing section (22) located in the housing (1); an end portion of the in-housing section (22) is inserted into the cooling liquid (11), and the out-of-housing section (21) is connected to the gas in an environment. The present pressure suppression pool apparatus is a passive system, has high safety and reliability, high cooling efficiency, and a significant pressure suppression effect, can effectively suppress the rise of the pressure and temperature of a containment under predetermined working conditions, and has low volume requirements for the space (12) and the cooling liquid (11).

公开(公告)号：EP4276854A1

公开(公告)日：2023-11-15

申请号：EP21918956.0

申请日：2021-09-27

申请人： China Nuclear Power Technology Research Institute Co., Ltd ,  China Nuclear Power Engineering Company Ltd. ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd.

发明人： LU, Xianghui ,  LIANG, Huo ,  LUO, Hanyan ,  YANG, Jiang ,  SHEN, Yonggang ,  LIANG, Ren

IPC分类号： G21C19/04 ,  G21C19/00 ,  G21C15/08 ,  G21C15/00

摘要： The present invention discloses a flow control device, a waste heat discharge system, and a flow stabilization method. The flow control device includes a first pressure sensor, a second pressure sensor, a temperature sensor, a flow control valve, and a controller. The first pressure sensor, the second pressure sensor, the temperature sensor, and the flow control valve are disposed in a return line of a condensate liquid. The first pressure sensor, the second pressure sensor, the temperature sensor and the flow control valve are each communicatively connected to the controller. The present invention is capable of automatically controlling the liquid level in the return line of the condensate liquid by means of a flow control system formed by the first pressure sensor, the second pressure sensor, the temperature sensor, the flow control valve and the processor. In addition, by setting the flow control system in the waste heat discharge system, the liquid level is maintained near the outlet of the heat exchanger, thereby preventing the condensate water from impacting on a gas-liquid interface, achieving the effect of eliminating the fluctuation of the flow rate of the condensate water, and realizing the flow stabilization effect of the waste heat discharge system.

公开(公告)号：EP4428876A1

公开(公告)日：2024-09-11

申请号：EP22888713.9

申请日：2022-01-11

申请人： China Nuclear Power Technology Research Institute Co., Ltd. ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd

发明人： LIANG, Huo ,  YANG, Jiang ,  SHEN, Yonggang ,  CHEN, Yichen ,  LIU, Jianchang ,  LU, Changdong ,  LIU, Zhonghao ,  CHEN, Yunyin ,  CUI, Xuyang ,  JI, Wenying ,  BAO, Xiaoli ,  WANG, Xianmao ,  OUYANG, Yong ,  LU, Xianghui ,  LIU, Jinlin

IPC分类号： G21C1/32 ,  G21C19/30 ,  G21C15/12

CPC分类号： Y02E30/30 ,  G21C1/322 ,  G21C15/12 ,  G21C19/30

摘要： A nuclear reaction device and a purification system. The nuclear reaction device comprises: a reaction vessel (100) provided with a reaction chamber (110) and a top cover (120) for sealing the reaction chamber (110); a reaction module (200) arranged in the reaction chamber (110), wherein the reaction module (200) reacts in the reaction chamber (110) and releases heat; a heat exchange module (300) arranged in the reaction chamber (110), wherein the heat exchange module (300) can absorb the heat released by the reaction module (200), an inlet of the heat exchange module (300) is configured to be in communication with a liquid supply system, and an outlet of the heat exchange module (300) is configured to be in communication with a thermally driven system.

公开(公告)号：EP4280228A1

公开(公告)日：2023-11-22

申请号：EP21918975.0

申请日：2021-10-21

申请人： China Nuclear Power Technology Research Institute Co., Ltd ,  China Nuclear Power Engineering Co., Ltd. ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd.

发明人： WANG, Xinxin ,  LU, Xianghui ,  CAI, Dechang ,  HE, Mingtao ,  DUAN, Rong ,  HAN, Song ,  FU, Xuefeng

IPC分类号： G21D3/16 ,  G21D3/00 ,  G21C7/08

摘要： The present disclosure relates to a method and apparatus for controlling a pressurized water reactor core, and a computer device and a storage medium. The method comprises: determining an operation mode of a pressurized water reactor core, wherein the pressurized water reactor core is loaded with at least one first control rod assembly, a second control rod assembly, a third control rod assembly and a plurality of fuel assemblies; acquiring a rod assembly control instruction corresponding to the operation mode; and according to the rod assembly control instruction, controlling the pressurized water reactor core on the basis of the first control rod assembly, the second control rod assembly and the third control rod assembly. By using the method, the aim of automatically controlling a pressurized water reactor core by means of a first control rod assembly, a second control rod assembly and a third control rod assembly is realized, and it is not necessary to control the pressurized water reactor core by frequently adjusting the concentration of boron in a primary circuit coolant, such that the control flow of the pressurized water reactor core is simplified, and thus the control efficiency of the pressurized water reactor core is improved.

公开(公告)号：EP4432302A1

公开(公告)日：2024-09-18

申请号：EP22894078.9

申请日：2022-01-13

申请人： China Nuclear Power Technology Research Institute Co., Ltd ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd. ,  China Nuclear Power Engineering Co., Ltd.

发明人： LU, Xianghui ,  HU, Yisong ,  FENG, Yingjie ,  ZHANG, Yijun ,  WANG, Weiru ,  HU, Yousen ,  LI, Kejia ,  HE, Mingtao ,  HUANG, Yu ,  WU, Yuting ,  CHEN, Tianming ,  MAO, Yulong ,  ZHANG, Wei ,  PENG, Sitao ,  CHENG, Yanhua

IPC分类号： G21C17/00 ,  G21C17/108

CPC分类号： Y02E30/30

摘要： An online protection method and system. The online protection method comprises: obtaining calibration state data that is periodically updated (S10); performing reconstruction calculation on reactor core power distribution data corresponding to the total rod positions of control rods (S20); obtaining the current total rod position of each control rod in real time, and selecting a group of reactor core power distribution data from a plurality of groups of reactor core power distribution data as the current reactor core power distribution data (S30); calculating a maximum LPD value and a minimum DNBR value corresponding to the current total rod position of the control rod (S40); and according to the calculated maximum LPD value, the calculated minimum DNBR value, a preset LPD setting value, and a preset DNBR setting value, determining whether to trigger a reactor shutdown signal (S50).

公开(公告)号：EP4427830A1

公开(公告)日：2024-09-11

申请号：EP22888715.4

申请日：2022-01-12

申请人： China Nuclear Power Technology Research Institute Co., Ltd. ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd. ,  China Nuclear Power Engineering Co., Ltd.

发明人： LIANG, Huo ,  LIU, Jinlin ,  BAO, Xiaoli ,  LU, Changdong ,  JI, Wenying ,  CUI, Xuyang ,  LIU, Zhonghao ,  WANG, Xianmao ,  CHEN, Yunyin ,  CHEN, Yichen ,  OUYANG, Yong ,  LU, Xianghui

IPC分类号： B01D45/02 ,  G21C15/16

摘要： A steam-water separator (10) and a waste heat removal system. The steam-water separator (10) comprises a separator body (100) and first connecting pipes (200). A first accommodation cavity (110) is provided in the separator body (100). A water inlet (120) in communication with the first accommodation cavity (110) is provided on one end of the separator body (100). The separator body (100) is provided with a plurality of first connecting holes (130) in communication with the first accommodation cavity (110). A plurality of first connecting pipes (200) are arranged. The number of first connecting pipes (200) is equal to the number of first connecting holes (130). The first connecting pipes (200) are connected to the first connecting holes (130) in a one-to-one correspondence manner.

公开(公告)号：EP4258287A1

公开(公告)日：2023-10-11

申请号：EP21902166.4

申请日：2021-09-27

申请人： China Nuclear Power Technology Research Institute Co., Ltd. ,  China General Nuclear Power Corporation ,  CGN Power Co., Ltd.

发明人： LIANG, Huo ,  CUI, Xuyang ,  LUO, Hanyan ,  CHEN, Yunyin ,  YANG, Jiang ,  LIU, Jinlin ,  WANG, Xianmao ,  JI, Wenying ,  LIU, Zhonghao ,  LU, Changdong ,  CHEN, Yichen ,  LIU, Jianchang ,  OUYANG, Yong ,  SHEN, Yonggang ,  LU, Xianghui

IPC分类号： G21C7/14

摘要： The present invention relates to the technical field of reactor system equipment and provides a control rod control device and a reactor. The control rod control device includes: an upper driving rod comprising an accommodating cavity in an interior of the upper driving rod; a lower driving rod; a trigger assembly including a trigger mechanism and a trigger pin, the trigger mechanism configured to keep the trigger pin in a locked state, the trigger mechanism operable to trigger displacement of the trigger pin when the upper drive rod moves upward with a certain acceleration; and a support member arranged at a junction between the upper driving rod and the lower driving rod and linked with the trigger pin. The present invention is used for automatically disconnecting the connection between the driving rod and a control rod assembly in the event of a rod ejection accident condition, so that the out-of-control rejection of a control rod is avoided, which ensures that a large amount of positive reactivity will not be introduced into the reactor core in a short period of time, reduces the probability of cladding damage, and improves the safety of the reactor.