Ling AO Nuclear Power Co., Ltd.

Chine

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2023 5
2022 4
2021 1
2020 2
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Classe IPC
C22C 16/00 - Alliages à base de zirconium 3
C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages 3
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages 3
C22C 1/02 - Fabrication des alliages non ferreux par fusion 2
G21C 7/10 - Structures des éléments de commande 2
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Résultats pour  brevets

1.

CONTROL ROD AND CONTROL ROD ASSEMBLY

      
Numéro d'application CN2022119579
Numéro de publication 2023/184891
Statut Délivré - en vigueur
Date de dépôt 2022-09-19
Date de publication 2023-10-05
Propriétaire
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD. (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Li, Zixi
  • Ren, Zhili
  • Pang, Zhengzheng
  • Lu, Yaheng
  • Peng, Yao

Abrégé

A control rod and a control rod assembly. The control rod comprises a core block (100), a bushing assembly (200), and a cladding (300); the bushing assembly (200) comprises a first bushing (210) sleeved on the core block (100); the cladding (300) is sleeved on the first bushing (210); the first bushing (210) is configured to form a constraint structure surrounding the core block (100) to limit the expansion of the core block (100) in a radial direction of the core block (100).

Classes IPC  ?

  • G21C 7/10 - Structures des éléments de commande

2.

HIGH-URANIUM-DENSITY ATF NUCLEAR FUEL PELLET AND PREPARATION METHOD THEREFOR

      
Numéro d'application CN2022070727
Numéro de publication 2023/130356
Statut Délivré - en vigueur
Date de dépôt 2022-01-07
Date de publication 2023-07-13
Propriétaire
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Chen, Mingzhou
  • Ren, Qisen
  • Liao, Yehong
  • Wang, Jiwei
  • Li, Lei
  • Guo, Daxi
  • Xie, Yiran
  • Wen, Jian
  • Li, Rui
  • Ge, Hongen
  • Zhang, Xiansheng
  • Chen, Mengteng
  • Zhang, Yongdong

Abrégé

A high-uranium-density ATF nuclear fuel pellet and a preparation method therefor. The high-uranium-density ATF nuclear fuel pellet comprises a columnar inner region (10), an isolation layer (20) covering the outer surface of the inner region (10), and a peripheral region (30) covering the isolation layer (20), wherein the inner region (10) is prepared from a nuclear fuel that is resistant to the oxidation of water and water vapor, and a high-uranium-density nuclear fuel; the peripheral area (30) is prepared from a nuclear fuel that is resistant to the oxidation of water and water vapor; and the mass of the high-uranium-density nuclear fuel accounts for 3-50% of the total mass of the inner region (10) and the isolation layer (20). The high-uranium-density ATF nuclear fuel pellet has an increased uranium loading amount and an effectively reduced central temperature, thereby improving the economical efficiency and safety of the operation of a reactor; and the use of the high-uranium-density nuclear fuel in a water-cooled nuclear reactor is realized, and the accident-tolerant capability of the nuclear reactor is improved.

Classes IPC  ?

  • G21C 3/62 - Combustible céramique
  • G21C 21/10 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par extrusion, filage, étirage

3.

CONTROL ROD FOR NUCLEAR FUEL AND CLADDING THEREOF

      
Numéro d'application CN2022120662
Numéro de publication 2023/098248
Statut Délivré - en vigueur
Date de dépôt 2022-09-22
Date de publication 2023-06-08
Propriétaire
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Ren, Zhili
  • Li, Weicai
  • Lu, Yaheng
  • Tang, Yangyang
  • Xue, Zhe
  • Pang, Zhengzheng

Abrégé

A control rod for nuclear fuel and a cladding thereof. The cladding of the control rod comprises a first cladding tube (10), a second cladding tube (20) and a bidirectional end plug (30) connected therebetween. A gas storage chamber (100) is formed in the first cladding tube (10), and an accommodating chamber (200) for holding an absorber (40) is formed in the second cladding tube (20). A through hole (300) penetrating through two opposite ends of the bidirectional end plug (30) is formed therein, the through hole (300) making the gas storage chamber (100) and the accommodating chamber (200) communicate. The cladding of the control rod comprises the separate parts which are connected into a whole by means of the bidirectional end plug (30). The first cladding tube (10) and the second cladding tube (20), as the separate parts of the cladding, are respectively used for forming the gas storage chamber (100) and holding the absorber (40). The gas storage chamber (100) is independent of the inner space in which the absorber (40) is placed and effectively stores a large amount of gas released when the absorber (40) absorbs neutrons, thereby avoiding expansion of the cladding tube in which the absorber (40) is arranged, and prolonging the service life of the cladding and the control rod.

Classes IPC  ?

  • G21C 7/10 - Structures des éléments de commande
  • G21C 7/103 - Ensembles de commande comportant un ou plusieurs absorbants ainsi que d'autres éléments, p. ex. combustibles ou modérateurs

4.

FUEL ASSEMBLY LOCKING DEVICE

      
Numéro d'application CN2021129129
Numéro de publication 2023/077468
Statut Délivré - en vigueur
Date de dépôt 2021-11-05
Date de publication 2023-05-11
Propriétaire
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Chen, Wei
  • Pang, Zhengzheng
  • Xue, Zhe
  • Tang, Yangyang
  • Ji, Shizhe
  • Su, Wen
  • Lu, Yaheng
  • Chen, Minli
  • Gong, Pengfeng
  • Ren, Zhili
  • Li, Weicai

Abrégé

Disclosed in the present invention is a fuel assembly locking device, comprising a locking piece disposed at the lower end of a fuel assembly and elastically engaged in a mounting hole of a lower core plate, and an anti-loosening mechanism disposed below the lower core plate and mated with the locking piece. The anti-loosening mechanism comprises a guide tube and an anti-loosening rod; the anti-loosening rod is disposed in the guide tube and moves back and forth between a first position and a second position in the axial direction of the guide tube; at the first position, an end part of the anti-loosening rod is ejected out of the guide pipe and mated in the locking piece, to prevent the locking piece from being disengaged from the mounting hole; at the second position, the end part of the anti-loosening rod is separated from the locking piece and retracted in the guide tube, so that the restriction on the locking piece is relieved. According to the fuel assembly locking device according to the present invention, the fuel assembly is fixed on the lower core plate by means of mating between the locking piece and the anti-loosening mechanism, the structure and operation are simple, and compared with an existing rotating mode, compact arrangement of fuel assemblies is facilitated.

Classes IPC  ?

  • G21C 3/12 - Moyens formant partie de l'élément pour le positionner dans le cœur du réacteurEntretoises extérieures à cet effet
  • G21C 5/06 - Moyens pour placer ou pour supporter les éléments combustibles
  • G21C 3/14 - Moyens formant partie de l'élément pour le placer ou le retirer du cœurMoyens pour assembler des éléments adjacents

5.

BLOWING-TYPE VENTILATION COOLING TOWER AND COOLING TOWER ARRANGEMENT SYSTEM

      
Numéro d'application CN2022103130
Numéro de publication 2023/024702
Statut Délivré - en vigueur
Date de dépôt 2022-06-30
Date de publication 2023-03-02
Propriétaire
  • CHINA NUCLEAR POWER ENGINEERING CO., LTD. (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA NUCLEAR POWER DESIGN COMPANY LTD. (SHENZHEN) (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD. (Chine)
Inventeur(s)
  • Xin, Wenjun
  • Cao, Yongwang
  • Chen, Jing
  • Nan, Wei
  • Luo, Lijuan
  • Zhang, Yangyang
  • Zhu, Qichao
  • Yue, Xinyi

Abrégé

A blowing-type ventilation cooling tower and a cooling tower arrangement system. The blowing-type ventilation cooling tower (100) comprises a fan chamber (20), an air intake channel (10) formed in an upper end of a side wall of the fan chamber (20) and provided with a downward opening, an air blower (60) arranged in the fan chamber (20), a rain area chamber (30) which is adjacent to and communicates with the fan chamber (20), a heat exchange chamber (40) which is arranged above the rain area chamber (30) and communicates with the rain area chamber (30), an air exhaust channel (50) which is arranged above the heat exchange chamber (40) and communicates with the heat exchange chamber (40), a water spraying device (80) arranged on the top in the heat exchange chamber (40) and used for introducing cooling water, and a water collecting tank (70) which is adjacent to and communicates with the rain area chamber (30), wherein an air outlet (51), away from the heat exchange chamber (40), of the air exhaust channel (50) is staggered from the heat exchange chamber (40). The blowing-type ventilation cooling tower (100) is suitable for an important service water system of a nuclear power plant, and heat exchange of cooling water for cooling is achieved; and the air intake channel and the air exhaust channel are improved, so that flying objects are effectively prevented from entering the tower so as not to damage members in the tower.

Classes IPC  ?

  • F28C 1/00 - Réfrigérants à ruissellement à contact direct, p. ex. tours de réfrigération
  • F28F 25/10 - Parties constitutives des réfrigérateurs à ruissellement pour l'alimentation en gaz ou en vapeur
  • F28F 19/01 - Prévention de la formation de dépôts ou de la corrosion, p. ex. en utilisant des filtres en utilisant des moyens pour séparer les éléments solides du fluide échangeur de chaleur, p. ex. des filtres
  • F28F 25/02 - Parties constitutives des réfrigérateurs à ruissellement pour répartir, faire circuler ou collecter le liquide
  • F28F 25/08 - Planches ou grilles d'éclaboussement, p. ex. pour convertir la pulvérisation de liquides en films de liquidesÉléments ou couches pour accroître l'aire de la surface de contact
  • F28F 25/06 - Buses ou canalisations de pulvérisation
  • F28F 25/04 - Augets répartiteurs ou collecteurs
  • G21D 1/02 - Dispositions d'équipement auxiliaire

6.

THREADED MEMBER MANUFACTURING METHOD AND THREAD MACHINING DEVICE

      
Numéro d'application CN2022103132
Numéro de publication 2022/247960
Statut Délivré - en vigueur
Date de dépôt 2022-06-30
Date de publication 2022-12-01
Propriétaire
  • CHINA NUCLEAR POWER ENGINEERING CO., LTD. (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD. (Chine)
Inventeur(s)
  • Zhao, Jianguang
  • Chen, Liang
  • Zhang, Jianping
  • Pang, Yibin
  • Zhu, Peng
  • Zhang, Feng
  • Ran, Xiaobing
  • Li, Xuejun
  • Wang, Long
  • Liu, Yanzhang
  • Xu, Guobing
  • Sun, Guang
  • Qiu, Zhensheng
  • Sun, Bingbing

Abrégé

A threaded member (10) manufacturing method and a thread machining device. The threaded member (10) manufacturing method comprises: S1, removing a failed screw section on a threaded member (10) and polishing an exposed cross section (110) flat; wherein a failure includes at least one of breakage, corrosion, and thread damage; S2, sleeving and fixing a connecting sleeve (20) on the periphery of an embedded section (11) of the threaded member (10), and polishing the top surface of the connecting sleeve (20) to be flush with the cross section (110); S3, forming a screw blank section (30) on the embedded section (11) and the connecting sleeve (20) by means of laser cladding; S4, machining the screw blank section (30) to a polished rod that is coaxial with the embedded section (11); S5, machining threads on the polished rod to form a new screw section (12), and connecting to the embedded section (11) to form an integral threaded member (10).

Classes IPC  ?

  • B23G 1/00 - FiletageMachines automatiques spécialement conçues pour le filetage
  • B23G 1/44 - Équipement ou accessoires spécialement conçus pour les machines ou dispositifs à fileter

7.

ZIRCONIUM ALLOY AND MANUFACTURING METHOD THEREFOR, CLADDING TUBE, AND FUEL ASSEMBLY

      
Numéro d'application CN2021117833
Numéro de publication 2022/213543
Statut Délivré - en vigueur
Date de dépôt 2021-09-10
Date de publication 2022-10-13
Propriétaire
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Shi, Lin
  • Gao, Changyuan
  • Chen, Minli
  • Chen, Liutao
  • Chen, Hansen
  • Xu, Yang
  • Wang, Xu
  • Zou, Hong
  • Nie, Lihong
  • Deng, Yongjun
  • Chen, Jianxin

Abrégé

Disclosed are a zirconium alloy and a manufacturing method therefor, a cladding tube, and a fuel assembly, wherein the zirconium alloy comprises the following components in percentages by mass: 1.20% to 1.40% of niobium, 0.03% to 0.07% of vanadium, 0.12% to 0.15% of oxygen, and the balance of zirconium. The zirconium alloy of the present invention has excellent corrosion resistance, can significantly reduce hydrogen absorption amount and improve high-temperature oxidation quenching resistance, has a more excellent corrosion resistance, a better hydrogen absorption resistance and a better embrittlement resistance after high-temperature oxidation quenching compared with an existing Zr-4 alloy, and is suitable for a fuel assembly of a nuclear power plant reactor and improves the service performance and safety performance of the fuel assembly as a cladding material of the fuel assembly.

Classes IPC  ?

  • C22C 16/00 - Alliages à base de zirconium
  • C22C 1/02 - Fabrication des alliages non ferreux par fusion
  • C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
  • G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages

8.

ZIRCONIUM ALLOY AND FABRICATION METHOD THEREFOR, CLADDING TUBE, AND FUEL ASSEMBLY

      
Numéro d'application CN2021117834
Numéro de publication 2022/213544
Statut Délivré - en vigueur
Date de dépôt 2021-09-10
Date de publication 2022-10-13
Propriétaire
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Gao, Changyuan
  • Xu, Yang
  • Chen, Liutao
  • Shi, Lin
  • Chen, Minli
  • Zhang, Libin
  • Wang, Xu
  • Zou, Hong
  • Nie, Lihong
  • Deng, Yongjun
  • Chen, Jianxin

Abrégé

Disclosed are a zirconium alloy and a fabrication method therefor, a cladding tube, and a fuel assembly, the zirconium alloy comprising the following components by mass percentage: 0.45%-0.95% of niobium, 0.21%-0.35% of tin, 0.03%-0.1% of iron, 0.03%-0.1% of vanadium, and 1000 ppm-1600 ppm of oxygen and the remainder is zirconium, wherein the total amount of iron and vanadium is ≤0.15%. The zirconium alloy of the present invention has excellent corrosion resistance and good embrittlement resistance after high-temperature oxidation and quenching by means of the ratio of the components, is suitable for cladding material of nuclear power plant reactors, and improves the service performance and safety of a fuel assembly.

Classes IPC  ?

  • C22C 16/00 - Alliages à base de zirconium
  • C22C 1/02 - Fabrication des alliages non ferreux par fusion
  • C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
  • G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages

9.

ZIRCONIUM ALLOY AND PREPARATION METHOD THEREFOR, CLADDING TUBE, AND FUEL ASSEMBLY

      
Numéro d'application CN2021117835
Numéro de publication 2022/213545
Statut Délivré - en vigueur
Date de dépôt 2021-09-10
Date de publication 2022-10-13
Propriétaire
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Chen, Liutao
  • Gao, Changyuan
  • Shi, Lin
  • Zhang, Libin
  • Wang, Xu
  • Chen, Minli
  • Chen, Hansen
  • Zou, Hong
  • Nie, Lihong
  • Deng, Yongjun
  • Chen, Jianxin

Abrégé

Disclosed are a zirconium alloy and a preparation method therefor, a cladding tube, and a fuel assembly. The zirconium alloy comprises the following components in percentages by mass: 0.48% to 0.95% of niobium, 0.37% to 0.75% of tin, 0.03% to 0.15% of iron, and 0 to 0.15% of vanadium, and further comprises 1100 ppm to 1600 ppm of oxygen and the balance of Zr, wherein the contents of niobium, iron and vanadium satisfy the following relationship: (Nb-0.45%)≥Fe+V and Fe+V≤0.2%. Due to the proportion of each component, the zirconium alloy of the present invention has a more excellent corrosion resistance and creep resistance compared with an existing Zr-4 alloy, and is suitable for cladding, grillwork and a guide tube of a fuel assembly of a nuclear power plant reactor and improves the service performance and safety performance of the fuel assembly.

Classes IPC  ?

  • C22C 16/00 - Alliages à base de zirconium
  • C22C 1/03 - Fabrication des alliages non ferreux par fusion utilisant des alliages-mères
  • C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
  • C21D 9/52 - Traitement thermique, p. ex. recuit, durcissement, trempe ou revenu, adapté à des objets particuliersFours à cet effet pour fils métalliquesTraitement thermique, p. ex. recuit, durcissement, trempe ou revenu, adapté à des objets particuliersFours à cet effet pour bandes métalliques
  • C21D 9/08 - Traitement thermique, p. ex. recuit, durcissement, trempe ou revenu, adapté à des objets particuliersFours à cet effet pour corps tubulaires ou tuyaux
  • B21J 5/00 - Méthodes pour forger, marteler ou presserÉquipement ou accessoires particuliers
  • G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages

10.

THREE-DIMENSIONAL LAYOUT METHOD, APPARATUS, AND DEVICE FOR PHYSICAL PROTECTION SYSTEM OF NUCLEAR POWER PLANT

      
Numéro d'application CN2020134873
Numéro de publication 2021/115322
Statut Délivré - en vigueur
Date de dépôt 2020-12-09
Date de publication 2021-06-17
Propriétaire
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA NUCLEAR POWER ENGINEERING CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD. (Chine)
Inventeur(s)
  • Liu, Jian
  • Liu, Guangming
  • Zhang, Jiwei
  • Li, Shuang
  • Li, Xiaofeng
  • Chen, Huaping
  • Liu, Xin
  • Wnag, Biyao
  • He, Haibo
  • Zhang, Lipeng
  • Lv, Zhihong

Abrégé

A three-dimensional layout method, apparatus, and device for a physical protection system of a nuclear power plant, the method comprising: loading a nuclear power plant three-dimensional model to be processed (S101); acquiring physical protection devices invoked by a user from a physical protection device model library, the physical protection devices including different models of intrusion detectors and cameras, each intrusion detector having corresponding detection performance parameters and each camera having corresponding surveillance performance parameters (S102); on the basis of a user operation, laying out the physical protection devices in predetermined positions of the nuclear power plant three-dimensional model and, on the basis of the performance parameters of the physical protection devices, visually displaying the effect in the nuclear power plant three-dimensional model (S103); and, after completing the layout, exporting a two-dimensional device layout diagram, an architectural diagram, and a device and material inventory (S104). Compared to the prior art, the present method can improve the design quality of the nuclear power plant physical protection system and reduce labour input.

Classes IPC  ?

11.

METHOD AND DEVICE FOR MEASURING CONTROL ROD WORTH IN SUBCRITICAL STATE OF NUCLEAR POWER PLANT

      
Numéro d'application CN2020087752
Numéro de publication 2020/221290
Statut Délivré - en vigueur
Date de dépôt 2020-04-29
Date de publication 2020-11-05
Propriétaire
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • GUANGDONG NUCLEAR POWER JOINT VENTURE CO., LTD. (Chine)
  • LING DONG NUCLEAR POWER CO., LTD. (Chine)
  • DAYA BAY NUCLEAR POWER OPERATIONS AND MANAGEMENT CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CHINA GUANGDONG NUCLEAR POWER CO., LTD. (Chine)
Inventeur(s) Tan, Shijie

Abrégé

A method and a device for measuring a control rod worth in a subcritical state of a nuclear power plant. The method comprises: acquiring a first neutron detector response value of a nuclear reactor in an initial state (S201); acquiring a second neutron detector response value of the nuclear reactor in a subcritical state (S202); and determining a control rod worth according to the first neutron detector response value and the second neutron detector response value (S203). The method and the device can measure the control rod worth without occupying a power detector, and the power detector can still play a protective role on the nuclear reactor, thereby improving the security of the nuclear reactor.

Classes IPC  ?

12.

ESTABLISHMENT METHOD FOR FUEL ROD CLADDING CREEP FINITE-LENGTH PIPE CORRECTION METHOD

      
Numéro d'application CN2019113442
Numéro de publication 2020/088375
Statut Délivré - en vigueur
Date de dépôt 2019-10-25
Date de publication 2020-05-07
Propriétaire
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Lu, Yong
  • Jin, Xin
  • Deng, Yongjun

Abrégé

Disclosed is an establishment method for a fuel rod cladding creep finite-length pipe correction method. The establishment method comprises: S1, determining parameters of a cladding pipe; S2, performing analysis and processing to obtain the ovalities of cladding pipes with different pipe lengths and different initial ovalities; S3, obtaining, according to the obtained ovalities of the cladding pipes with different pipe lengths and different initial ovalities and in conjunction with internal and external pressure differences of the cladding pipes, the rigidities of the cladding pipes with different pipe lengths and different initial ovalities; S4, obtaining a cladding pipe correction factor F; and S5, according to the analysis of the influence of the pipe lengths and the initial ovalities of the cladding pipes and the internal and external pressure differences of the cladding pipes on the cladding pipe correction factor, determining a curve of a finite-length pipe correction factor, and establishing a finite-length pipe correction method. By means of the method, the problem of an end boundary condition affecting a cladding creep behavior in fuel rod cladding creep collapse analysis is solved, the rationality and reliability of fuel rod cladding creep analysis are improved, and the cladding creep collapse analysis reliability of a fuel rod in engineering analysis and designs is guaranteed.

Classes IPC  ?

  • G06F 17/00 - Équipement ou méthodes de traitement de données ou de calcul numérique, spécialement adaptés à des fonctions spécifiques

13.

POSITIONING GRID AND FUEL ASSEMBLY

      
Numéro d'application CN2017102497
Numéro de publication 2019/056222
Statut Délivré - en vigueur
Date de dépôt 2017-09-20
Date de publication 2019-03-28
Propriétaire
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD. (Chine)
Inventeur(s)
  • Pang, Zhengzheng
  • Zhang, Yuxiang
  • Li, Weicai
  • Ji, Shizhe

Abrégé

A positioning grid and fuel assembly, the positioning grid comprising two grille units (10) and a clamp unit (20); the two grille units (10) are disposed in an opposing vertical configuration and the clamp unit (20) is inserted between the grille units (10), and can oppose the vertical movement of the grille units (10). The positioning grid of the fuel assembly can reduce stress on guide tubes, reduce fuel assembly growth and ensure lateral rigidity of fuel assemblies, preventing bending of fuel assemblies during normal operation and controlling difficulties in rod insertion, increasing strength of the positioning grid and stability of the coolant circulation channel under accident conditions.

Classes IPC  ?

14.

FUEL ASSEMBLY AND METHOD FOR ASSEMBLING SAME

      
Numéro d'application CN2017085415
Numéro de publication 2018/214006
Statut Délivré - en vigueur
Date de dépôt 2017-05-22
Date de publication 2018-11-29
Propriétaire
  • LING DONG NUCLEAR POWER CO., LTD. (Chine)
  • LING AO NUCLEAR POWER CO., LTD. (Chine)
  • CHINA NUCLEAR POWER ENGINEERING CO., LTD (Chine)
  • CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE CO., LTD (Chine)
  • CHINA GENERAL NUCLEAR POWER CORPORATION (Chine)
  • CGN POWER CO., LTD (Chine)
Inventeur(s)
  • Li, Weicai
  • Yu, Wenchi
  • Fu, Xiangang
  • Zhou, Yuemin
  • Zhang, Guoliang
  • Chen, Jianxin

Abrégé

Provided are a fuel assembly and a method for assembling same. The fuel assembly comprises a lattice frame and fuel rods (14) mounted in the lattice frame in a longitudinal direction, wherein the lattice frame comprises a plurality of strips (131), the strips (131) are intersected and matched with each other to form a plurality of grid units (130), the fuel rods (14) are correspondingly located inside the grid units (130), the strip (131) is further provided with a blending wing (16), the strip (131) and the blending wing (16) are of an integral structure formed by punching, and the blending wing (16) further comprises a secondary forming part. Since the secondary forming preparation precision has been improved, influences caused by a dimensional tolerance and an assembling tolerance are reduced, thereby enhancing the generated transverse flow, and improving efficacy of a coolant fluid. Moreover, fluid layers on the surfaces of the fuel rods (14) are effectively destroyed in the vicinity of the fuel rods (14), enhancing the blending effect.

Classes IPC  ?

  • G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles