公开(公告)号：EP4459497A1

公开(公告)日：2024-11-06

申请号：EP22913678.3

申请日：2022-10-18

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

发明人： DING, Peng ,  CHEN, Shu ,  LI, Wenhuai ,  XIA, Wenqing ,  YU, Fengwan ,  DUAN, Chengjie ,  CUI, Dawei ,  LIN, Jiming

IPC分类号： G06F30/27

摘要： A nuclear reactor design scheme optimization method and apparatus, a computer device, a storage medium, and a computer program product. The method comprises: acquiring an overall machine learning model of a nuclear reactor; according to the overall machine learning model of the nuclear reactor, searching for a nuclear reactor design scheme using an optimization algorithm, to obtain a nuclear reactor design scheme search result; performing validation and regression of the nuclear reactor design scheme search result; and generating an optimized nuclear reactor design scheme according to a validation and regression result. In the whole process, diversified nuclear reactor design schemes are generated using a machine learning model, and an optimization algorithm is used to perform a search of the schemes, and to perform subsequent validation and regression, so that an optimized nuclear reactor design scheme can be generated efficiently while ensuring the accuracy of scheme construction.

公开(公告)号：EP4280227A1

公开(公告)日：2023-11-22

申请号：EP22748792.3

申请日：2022-01-05

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

发明人： XUE, Zhe ,  PANG, Zhengzheng ,  LI, Weicai

IPC分类号： G21C7/103 ,  G21C7/10 ,  G21C7/11

摘要： A control rod absorber assembly (1), a control rod (3) and a control rod assembly. The control rod absorber assembly (1) comprises a first absorber (11), a second absorber (12) and a stress transmission assembly (13), wherein the stress transmission assembly (13) is arranged around the periphery of the second absorber (12) and forms a stress combination together with the second absorber (12), and a receding space (2) for accommodating the second absorber (12) when the second absorber expands in a radial direction is provided between the stress transmission assembly (13) and the periphery of the second absorber (12); and the first absorber (11) and the stress combination are configured to be mounted in a cladding tube (31) of a control rod (3), the first absorber (11) and the stress combination are arranged in an axial direction of the cladding tube (31),and the first absorber (11) is located above the stress combination and is configured for pressing the stress combination downwards. By arranging the stress transmission assembly (13), the second absorber (12) does not bear the action of gravity of the first absorber (11), so as to reduce compression creep of the second absorber (12); and when the second absorber (12) absorbs neutrons and expands in the radial direction, an expanded portion can be accommodated in a receding space (2), so as to prevent a cladding tube (31) from being damaged.

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：EP3985685A1

公开(公告)日：2022-04-20

申请号：EP20912993.1

申请日：2020-01-07

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

发明人： ZHAN, Dekui ,  ZHAO, Xinhai ,  XIA, Shaoxiong ,  CHEN, Peng ,  FU, Hui ,  WU, Zijie

IPC分类号： G21C15/18

摘要： A safety system for dealing with a severe accident of a nuclear power plant and a control method therefor. The safety system includes at least one in-reactor water injection system for injecting water into a reactor pressure vessel; each in-reactor water injection system includes a multi-stage accumulator, and a first water injection pipeline connected to a cold pipe of a primary loop system; an interior space of the multi-stage accumulator includes a gas-phase space, a first-stage water injection space, and a second-stage water injection space distributed from top to bottom in sequence; the multi-stage accumulator is provided with a first flow pipeline and a second flow pipeline having a pipe diameter less than that of the first flow pipeline, the first flow pipeline communicates the first-stage water injection space with the first water injection pipeline, and the second flow pipeline communicates the second-stage water injection space with the first water injection pipeline. In the present disclosure, both in-reactor and outer-reactor cooling may be conducted by the in-reactor water injection system in conjunction with an outer-reactor cooling water injection system, thereby maintaining the integrity of the RPV when a severe accident occurs.

公开(公告)号：EP3979260A1

公开(公告)日：2022-04-06

申请号：EP19957791.7

申请日：2019-12-25

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

发明人： ZHAN, Dekui ,  LIANG, Junming ,  CHEN, Peng ,  XIA, Shaoxiong ,  ZHANG, Huiyong ,  FU, Hui ,  ZHANG, Lei ,  WU, Zijie

IPC分类号： G21C17/00

摘要： A test system, and a heating and temperature measuring device for simulating RPV heat exchange characteristics of a nuclear power plant. The heating and temperature measuring device includes a tube portion, a hemispherical lower head connected to a lower end of the tube portion, a heating assembly for heating the lower head, and a temperature measuring assembly disposed in the lower head. The temperature measuring assembly is configured to monitor a temperature change in a wall thickness direction of the lower head to monitor a surface temperature change of the lower head. The test system for simulating the RPV heat exchange characteristics of the nuclear power plant is used for simulating a process that a high-temperature core melt is transferred to an RPV wall surface and flows outside of the RPV wall surface under the condition that a severe accident occurs to the nuclear power plant, thereby studying the distribution of CHF and three-dimensional cooling water flow characteristics at different positions on an RPV outer wall surface under a three-dimensional flow condition, thereby providing data support for studying the effectiveness of a severe accident mitigation system -a pit water injection system.

公开(公告)号：EP3086324B1

公开(公告)日：2019-03-20

申请号：EP13899373.8

申请日：2013-12-20

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

发明人： YU, Wenchi ,  LI, Weicai ,  HU, Haixiang ,  WANG, Jiayuan

IPC分类号： G21C3/32 ,  G21C3/33

公开(公告)号：EP4451291A1

公开(公告)日：2024-10-23

申请号：EP22918269.6

申请日：2022-10-31

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 ,  JI, Wenying ,  SHEN, Yonggang ,  CUI, Xuyang ,  OUYANG, Tailong ,  OUYANG, Yong ,  WANG, Xiong ,  LU, Changdong ,  CHEN, Yunyin ,  LIU, Jianchang ,  WANG, Xianmao ,  LIU, Zhonghao ,  CHEN, Yichen ,  BAO, Xiaoli

IPC分类号： G21F5/08 ,  G21F5/06

摘要： According to the nuclear fuel transportation container provided by the present invention, a tank body for accommodating nuclear fuel assemblies is wrapped in a plastically deformable impact-resistant protective layer, and several recesses for accommodating supporting columns are formed in the protective layer, so that the supporting columns can abut against the tank body and bear the weight of the container, the protective layer does not bear weight, and an energy absorption structure is used to plastically deform and resist impact,so that the impact resistance is improved.

公开(公告)号：EP4421824A1

公开(公告)日：2024-08-28

申请号：EP21962231.3

申请日：2021-12-16

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

发明人： XUE, Jiaxiang ,  WU, Lixiang ,  ZHANG, Xiansheng ,  REN, Qisen ,  LIAO, Yehong ,  ZHANG, Yongdong

IPC分类号： G21C3/04 ,  G21C3/16

CPC分类号： Y02E30/30 ,  G21C3/16 ,  G21C3/042 ,  G21C3/044

摘要： Disclosed in the present invention are a fuel module and an application thereof. The fuel module comprises a column structure, a plurality of hollow closed holes and a plurality of cooling through holes that are dispersedly provided in the column structure, and fuel provided in the column structure; the hollow closed holes are located in the column structure; each of the hollow closed holes is filled with fuel; the cooling through holes are isolated from the hollow closed holes, run through two opposite sides of the column structure, and are used for allowing a cooling medium to pass through. In the fuel module of the present invention, a column structure is used as a supporting body, and hollow closed holes are filled with fuel and cooperate with cooling through holes to form an integrated structure. Compared with the cladding-pellet-assembly structure of an existing fuel assembly, the overall structure has high strength, and the fuel module can withstand high pressure, is safe and reliable, and improves the safety of a nuclear reactor.

公开(公告)号：EP4230336A1

公开(公告)日：2023-08-23

申请号：EP21890809.3

申请日：2021-09-17

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

发明人： XUE, Jiaxiang ,  LIAO, Yehong ,  REN, Qisen ,  LIU, Tong ,  ZHAI, Jianhan ,  MA, Haibin ,  ZHANG, Xiansheng ,  ZHANG, Yongdong ,  LI, Rui ,  LIU, Yang

IPC分类号： B23K1/008 ,  B23K1/19

摘要： A brazing connection method for a silicon carbide cladding, comprising the following steps: S1, using Al and Si as connection materials, providing the connection materials between a cladding pipe and an end plug which are matched with each other, forming a middle connection material of an Al/Si/Al three-layer structure, and forming, by means of the middle connection material, the cladding pipe, and the end plug, an assembly to be connected; and S2, placing said assembly in a vacuum or inert atmosphere for brazing connection, the middle connection material forming a connection layer, and connecting the cladding pipe and the end plug into a whole. The present invention further relates to a silicon carbide cladding formed by the method, a fuel rod comprising same, and a fuel assembly. In the present brazing connection method, Al and Si are used as the connection materials, and the connection layer of the Al/Si/Al three-layer structure is formed between the cladding pipe and the end plug, such that high-strength and reliable connection of the SiC cladding is achieved, and the SiC cladding is good in high-temperature resistance and hydrothermal corrosion resistance, thereby meeting nuclear application requirements.