WO2024098261A1 - Structure de pastille de combustible nucléaire de type fendu, et barre de combustible ayant une gaine en composite sic - Google Patents

Structure de pastille de combustible nucléaire de type fendu, et barre de combustible ayant une gaine en composite sic Download PDF

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Publication number
WO2024098261A1
WO2024098261A1 PCT/CN2022/130706 CN2022130706W WO2024098261A1 WO 2024098261 A1 WO2024098261 A1 WO 2024098261A1 CN 2022130706 W CN2022130706 W CN 2022130706W WO 2024098261 A1 WO2024098261 A1 WO 2024098261A1
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WO
WIPO (PCT)
Prior art keywords
cavity
core block
pellet
elastic member
nuclear fuel
Prior art date
Application number
PCT/CN2022/130706
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English (en)
Chinese (zh)
Inventor
卢志威
薛佳祥
吴利翔
刘洋
张显生
陈迎红
杨荣坤
廖业宏
Original Assignee
中广核研究院有限公司
岭东核电有限公司
中国广核集团有限公司
中国广核电力股份有限公司
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Application filed by 中广核研究院有限公司, 岭东核电有限公司, 中国广核集团有限公司, 中国广核电力股份有限公司 filed Critical 中广核研究院有限公司
Priority to PCT/CN2022/130706 priority Critical patent/WO2024098261A1/fr
Publication of WO2024098261A1 publication Critical patent/WO2024098261A1/fr

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to the technical field of nuclear fuel, and in particular to a petal-type nuclear fuel pellet structure and a SiC composite material cladding fuel rod.
  • the core of a nuclear power plant is composed of multiple fuel assemblies.
  • One type of fuel assembly consists of a rigid frame and fuel rods.
  • the fuel rods are arranged in parallel and evenly spaced in the rigid frame.
  • the fuel rods are composed of a cladding tube, a fuel pellet, an air cavity spring, an upper end plug and a lower end plug. After the fuel pellet and the air cavity spring are loaded into the cladding tube, the upper end plug and the lower end plug are welded at the upper and lower ends to form a fuel rod.
  • the cladding tube is generally made of zirconium alloy.
  • SiC composites Compared with zirconium alloys, SiC composites have significant advantages in high-temperature strength, radiation stability, creep resistance, oxidation resistance, and wear resistance. They also have significant fault tolerance potential under light water reactor accident conditions. Therefore, nuclear fuel cladding with SiC composite materials has become a key research direction internationally.
  • SiC composite materials have good strength, creep resistance and other properties, they are ceramic brittle materials. Compared with the metal cladding used in the current traditional UO2-Zr fuel system, their ductility is lower. When a small amount of bending or strain occurs, cracks are easily generated. The generation of cracks may lead to the effectiveness of fuel rod sealing and affect the safe operation of the reactor.
  • SiC composite materials Due to the performance characteristics of the above-mentioned SiC composite materials, when it is used as the cladding of the fuel rod, it is necessary to make a refined design of the gap between the pellet and the cladding. Because SiC composite materials belong to ceramic materials, they have basically no plasticity, and the elastic modulus is larger than that of traditional zirconium alloy claddings. Therefore, it is necessary to consider the design of the fuel rods to avoid serious pellet-cladding interactions during actual operation in the reactor. Because once the pellets come into contact with the cladding, the intrinsic strains of the pellets such as radiation swelling and thermal expansion will cause the SiC composite cladding to produce greater stress and strain; and the SiC composite cladding's ability to withstand strain is limited, and structural damage is very likely to occur. Therefore, the design of the prior art often needs to consider designing a larger pellet-cladding gap value to avoid serious pellet-cladding interactions.
  • the pellet-cladding in the SiC composite cladding fuel rod is a gap design, but based on the design scheme of the prior art, the inventors found that it has the following defects:
  • the core block is installed in the cladding tube.
  • the outer diameter of the core block is generally smaller than the inner diameter of the cladding.
  • the larger core block-cladding gap will inevitably make it difficult to ensure that the core block is completely centered in the cladding during actual operation.
  • the following problems will occur if the core block is not centered in the cladding: one side of the core block will be close to the cladding, while the other side will be far away from the cladding, so there will be uneven circumferential heat transfer of the fuel rod.
  • the area close to the cladding has a smaller heat transfer resistance and a larger heat flow, so the temperature of the cladding will also be higher; while the area far from the cladding is the opposite; at the same time, when the SiC cladding is operated under irradiation conditions in the reactor, irradiation swelling will occur, and this irradiation swelling is related to the irradiation temperature in addition to the irradiation dose.
  • the higher the temperature the smaller the irradiation swelling. Therefore, if the circumferential temperature of the SiC cladding is uneven, uneven irradiation swelling will occur, which will cause the fuel rod to bend, affecting its operational safety.
  • the technical problem to be solved by the present invention is to provide an improved split-petal nuclear fuel pellet structure and a SiC composite material cladding fuel rod.
  • the technical solution adopted by the present invention to solve the technical problem is: to provide a split-petal nuclear fuel pellet structure, which includes a pellet and an elastic member;
  • a cavity for accommodating the elastic member is provided in the middle of the core block
  • the core block comprises at least two radially matched core block petals, and the elastic member is accommodated in the cavity and abuts against each of the core block petals.
  • the cavity is arranged to extend along the axial direction of the core block
  • the elastic member is an elastic tube, which is placed in the cavity along the extension direction of the cavity.
  • the number of the core block petals is two, and the elastic member is an elliptical tube;
  • the elastic member abuts against the core block petal with its circumference corresponding to the major axis of the ellipse, and a first gap is formed between the circumference of the elastic member corresponding to the minor axis of the ellipse and the core block petal, and the first gap is used to accommodate the elastic deformation of the elastic member.
  • an inner curvature is formed on the elastic member in a concave manner on the circumference corresponding to the minor axis of the ellipse.
  • the number of the core block petals is at least three, and the circumferential surface of the elastic member is provided with at least three first protrusions protruding outward and abutting against the core block petals, recesses are formed correspondingly between adjacent first protrusions, and a first gap is formed between the recessed portions and the core block petals, and the first gap is used to accommodate the elastic deformation of the elastic member.
  • At least one through hole is formed on the circumferential surface of the elastic member.
  • the elastic member is a spring, and the number of the core block petals is two;
  • the relative mating surfaces of the two core block petals are respectively concave, forming the cavity on each core block petal; the elastic member is accommodated in the cavity of the two core block petals, and its two opposite ends are respectively pressed against the inner bottom surface of the cavity of the two core block petals.
  • the cavity is in a stepped hole shape, including a first cavity and a second cavity that are connected, the inner circumference of the first cavity is larger than the inner circumference of the second cavity, the first cavity is close to the central axis of the core block, and the second cavity is far from the central axis of the core block.
  • a second gap is formed between the opposite mating surfaces of adjacent core block petals, and the second gap is used to accommodate the deformation of the core block petals.
  • the width of the second gap is 0.2% to 15% of the overall diameter of the core block.
  • the second gaps are distributed symmetrically with respect to the central axis of the core block.
  • one end surface of the core block is concavely formed with a positioning groove, and the other end surface opposite thereto is convexly formed with a second protrusion;
  • Adjacent core blocks are axially positioned by the cooperation of the positioning groove and the second protrusion.
  • the present invention also provides a SiC composite cladding fuel rod, which comprises the petal-type nuclear fuel pellet structure described in any one of the above, a SiC composite cladding tube, an air cavity spring, an upper end plug and a lower end plug;
  • the upper end plug and the lower end plug are respectively connected to the upper end and the lower end of the SiC composite cladding tube;
  • a plurality of the petal-type nuclear fuel pellet structures are sequentially stacked in the inner cavity of the SiC composite material cladding tube along the axial direction of the SiC composite material cladding tube;
  • the air cavity spring is arranged in the inner cavity of the SiC composite material cladding tube and is connected between the petal-type nuclear fuel core block structure and the upper end plug.
  • each core block petal is closely attached to the inner wall of the nuclear fuel cladding tube with its outer wall surface, so that the core block and the nuclear fuel cladding tube are tightly matched without gaps, which can ensure uniform circumferential heat transfer of the fuel rod and avoid the bending of the fuel rod caused by uneven irradiation swelling of the cladding; the core block petal can produce elastic displacement under the support of the elastic member, avoiding transient hard contact between the cladding and the core block petal, thereby ensuring that the core block and the cladding are tightly matched without gaps, and no large reaction force is generated on the cladding.
  • the core block design with a cavity in the middle can further reduce the operating peak temperature of the core block, and the cavity can accommodate more fission gas, thereby reducing the internal pressure of the fuel rod.
  • FIG1 is a top view of a split-type nuclear fuel pellet structure according to a first embodiment of the present invention
  • FIG2 is a top view of a split-petal nuclear fuel pellet structure according to a second embodiment of the present invention.
  • FIG3 is a top view of a split-petal nuclear fuel pellet structure according to a third embodiment of the present invention.
  • FIG4 is a top view of a split-petal nuclear fuel pellet structure according to a fourth embodiment of the present invention.
  • FIG. 5 is a schematic structural diagram of an elastic member of a petal-type nuclear fuel pellet structure according to a fifth embodiment of the present invention.
  • FIG6 is a schematic structural diagram of a split-petal nuclear fuel pellet structure according to a sixth embodiment of the present invention.
  • FIG7 is a schematic structural diagram of a petal-type nuclear fuel pellet structure according to a seventh embodiment of the present invention.
  • FIG8 is a schematic diagram of the structure of FIG7 from another perspective
  • FIG. 9 is a schematic diagram of the structure of a SiC composite cladding fuel rod according to some embodiments of the present invention.
  • axial direction and radial direction refer to the length direction of the entire device or component as the “axial direction” and the direction perpendicular to the axial direction as the "radial direction”.
  • the split-flap nuclear fuel pellet structure of the present invention comprises a pellet 1 and an elastic member 2.
  • the pellet 1 and the elastic member 2 are both accommodated in the inner cavity of a nuclear fuel cladding tube 3 (hereinafter referred to as cladding tube 3).
  • a cavity 11 for accommodating the elastic member 2 is provided in the middle of the core block 1 .
  • the core block 1 includes at least two radially matched core block petals 10, each core block petal 10 includes an inner wall surface 101 facing the central axis of the core block 1 and an outer wall surface 102 facing away from the central axis of the core block 1, and the elastic member 2 abuts against the inner wall surface 101 of each core block petal 10 in the cavity 11, pushing the outer wall surface 102 of the core block petal 10 to fit tightly against the inner wall of the cladding tube 3.
  • each core block petal 10 is pushed by the elastic member 2 to cling to the inner wall of the nuclear fuel cladding tube 3 with its outer wall surface 102, so that there is a tight fit without gaps between the core block 1 and the cladding tube 3, which can ensure that the circumferential temperature of the cladding tube 3 is relatively uniform, that is, the circumferential heat transfer of the fuel rod is uniform, thereby avoiding the bending of the fuel rod caused by the uneven irradiation swelling of the cladding tube 3.
  • the core block flap 10 can produce elastic displacement under the support of the elastic member 2, thereby avoiding transient hard contact between the cladding tube 3 and the core block flap 10, thereby ensuring that the core block 1 and the cladding tube 3 are designed to fit tightly without gaps, while not generating a large reaction force on the cladding tube 3.
  • the design of the pellet 1 with a cavity 11 in the middle can further reduce the operating peak temperature of the pellet 1, and the cavity 11 can accommodate more fission gas, thereby reducing the internal pressure of the fuel rod.
  • the elastic member 2 may be an elastic tube or a spring.
  • the elastic tube is placed in the cavity 11 along the extension direction of the cavity 11, and the elastic tube may be an elastic thin-walled tube.
  • the elastic member 2 is an elliptical tube, and the number of the pellet petals 10 is two.
  • the cavity 11 may extend along the axial direction of the core block 1 to the opposite end surfaces that pass through the core block 1 , and the two core block petals 10 are arranged opposite to each other to form an approximately complete hollow core block 1 .
  • the cross-sectional shape of the cavity 11 in the middle of the core block 1 can also be approximately elliptical.
  • the assembly positioning point is located at the apex of the elliptical major axis of the elastic member 2 and the core block petal 10.
  • the elliptical major axis of the elastic member 2 can be slightly larger than the elliptical major axis of the cavity 11. Therefore, after the components are assembled, the core block petal 10 can be pushed by the force of the elastic member 2 so that its outer wall surface 102 is close to the inner wall of the cladding tube 3.
  • the elastic member 2 can abut against the inner wall surface 101 of the core block petal 10 with its circumferential surface corresponding to the major axis of the ellipse, and a first gap 41 is formed between the circumferential surface of the elastic member 2 corresponding to the minor axis of the ellipse and the inner wall surface 101 of the core block petal 10, and the first gap 41 is used to accommodate the elastic deformation of the elastic member 2.
  • the inner curvature can be formed by the circumference of the elastic member 2 corresponding to the minor axis of the ellipse being concave in the radial direction of the minor axis of the ellipse.
  • the inner curvature can be roughly in the shape of a U-shaped groove.
  • the inner curvature can also be roughly in the shape of a curved wave.
  • the inner curved portion 20 can also reduce the overall stiffness of the elastic member 2, thereby preventing too much stress from being generated after the core block 1 and the cladding tube 3 come into contact.
  • the difference from the above embodiments is that: the number of pellet petals 10 is three, and the circumferential surface of the elastic member 2 has three first protrusions protruding outward and abutting against the inner wall surface 101 of the pellet petals 10, and each first protrusion abuts against the inner wall surface 101 of each pellet petal 10. Recesses are formed correspondingly between adjacent first protrusions, and a first gap 41 is formed between the recesses and the inner wall surface 101 of the pellet petals 10, and the first gap 41 is used to accommodate the elastic deformation of the elastic member 2.
  • the number of pellet petals 10 is four.
  • Recesses are formed correspondingly between adjacent first protrusions, and a first gap 41 is formed between the recessed portions and the inner wall surface 101 of the pellet petal 10, and the first gap 41 is used to accommodate the elastic deformation of the elastic member 2.
  • a third protrusion is formed between adjacent recessed portions to further accommodate the elastic deformation of the elastic member 2 and improve the overall rigidity of the elastic member 2.
  • the third protrusion may be provided corresponding to the second gap 42 between the core block petals 10.
  • the cross-sectional shape of the cavity 11 in the middle of the core block 1 can be set to correspond to the cross-sectional shape of the elastic member 2, so that the two are roughly the same shape, so that the elastic member 2 has better coaxiality with the core block 1 in the cavity 11.
  • the elastic member 2 in order to further reduce the rigidity of the elastic member 2, when the elastic member 2 is an elastic tube, in order to prevent the elastic force between the elastic member 2 and the pellet petal 10 from being too large due to the large rigidity of the elastic member 2, at least one through hole 20 is opened on the circumference of the elastic member 2.
  • the through holes 20 can be distributed on the elastic member 2 at intervals along the axial direction of the elastic member 2.
  • the size and number of the through holes 20 can be further determined by considering factors such as the elastic force to be satisfied, without affecting the role of the elastic member 2 itself in the corresponding technical solution described in combination with the embodiments disclosed in the present invention.
  • the elastic member 2 is a spring, specifically, it can be a coil spring.
  • the relative mating surfaces of the two core block petals 10 are respectively concave to form a cavity 11, and the elastic member 2 is accommodated in the cavity 11 of the two core block petals 10, and its two opposite ends are respectively pressed against the inner bottom surface 103 of the cavity 11 of the two core block petals 10.
  • the inner wall surface 101 of the two core block petals 10 can be concave inward along the radial direction of the core block 1 to form a cavity 11, and the elastic member 2 is accommodated in the cavity 11 of the two core block petals 10, and its opposite ends can be pressed against the inner bottom surface 103 of the cavity 11 of the two core block petals 10 along the radial direction of the core block 1.
  • the cavity 11 may be a blind hole similar to a certain depth
  • the elastic member 2 is disposed in the blind hole in a horizontal direction as a whole, and its two opposite ends are connected and fixed to the inner wall surfaces 101 of the two core block petals 10.
  • the elastic deformation of the elastic member 2 can be used to push the two oppositely arranged core block petals 10, so that the outer wall surfaces 102 of the two core block petals 10 are tightly fitted on the inner wall of the cladding tube 3, thereby forming a gap-free tight fit state between the core block 1 and the cladding tube 3.
  • the cavity 11 may be in a stepped hole shape.
  • the cavity 11 may include a first cavity 111 and a second cavity 112 that are connected, the inner circumference of the first cavity 111 is larger than the inner circumference of the second cavity 112, the first cavity 111 is close to the central axis of the core block 1, and the second cavity 112 is far from the central axis of the core block 1.
  • first cavity 111 or the second cavity 112 When the first cavity 111 or the second cavity 112 is a circular hole, its inner circumference size refers to the inner diameter. When the first cavity 111 or the second cavity 112 is a square hole, its inner circumference size refers to the inner circumference width. When the first cavity 111 or the second cavity 112 is a rectangular hole, its inner circumference size refers to the inner circumference width. When the first cavity 111 or the second cavity 112 is a hole of other shapes, its inner circumference size may refer to the maximum width of the inner circumference.
  • the two opposite ends of the elastic member 2 abut against the inner wall surfaces 101 of the two core block petals 10 in the second cavity 112 , and the middle portion of the elastic member 2 is located in the first cavity 111 and spaced apart from the inner wall surfaces 101 of the core block petals 10 .
  • the cavity 11 exists in the form of a stepped hole, so that the high-temperature area in the center of the core block 1 is separated from the middle part of the elastic member 2 by a certain distance, thereby reducing the operating temperature of the elastic member 2 and reducing the risk of stress relaxation or melting thereof.
  • a second gap 42 may be formed between the relative mating surfaces of adjacent core block petals 10, and the second gap 42 is used to adapt to the deformation of the core block petals 10 and leave a deformation margin for the volume change of the core block petals 10.
  • the core block 1 when the heating power of the fuel rod increases abnormally, the core block 1 will produce intrinsic volume changes such as radiation swelling and thermal expansion.
  • the deformation margin between two adjacent core block petals 10 can be used to accommodate the above-mentioned intrinsic volume changes and prevent the core block 1 from deforming outward and exerting a large force on the cladding tube 3.
  • the width of the second gap 42 can be 0.2% to 15% of the overall diameter of the core block 1, so as to allow a deformation margin for the volume change of the core block petals 10 while achieving better circumferential heat transfer distribution of the cladding.
  • the second gaps 42 are symmetrically distributed relative to the central axis of the core block 1, so that the core block 1 has a more uniform circumferential heat transfer distribution effect in the cladding tube 3.
  • the second gaps 42 are relatively symmetrically distributed with the central axis of the core block 1 as the axis; when the number of the core block petals 10 is three or more, the second gaps 42 are centrally symmetrically distributed with the central axis of the core block 1 as the axis.
  • each core block 1 is concave to form a positioning groove 70, and the other opposite end face is convex to form a second protrusion 71; the core blocks 1 adjacent to each other along the axial direction can be axially positioned by matching the positioning groove 70 and the second protrusion 71.
  • the arrangement of the positioning groove 70 and the second protrusion 71 ensures that two axially adjacent core block petals 10 have a better circumferential fit.
  • the circumferential positions of multiple axial core block petals 10 remain the same, thereby ensuring that the core block petals 10 at different axial heights have the same circumferential structure and heat transfer performance, and the cavities 11 and elastic parts 2 at different axial heights can also be maintained at approximately the same position, so that the petal-type nuclear fuel core block structure has better integrity in the cladding tube 3, ensuring that the overall circumferential temperature of the cladding tube 3 is uniform, and avoiding the occurrence of fuel rod bending caused by uneven circumferential radiation swelling of the cladding tube 3.
  • the material of the pellet petals 10 can be uranium dioxide, uranium silicide, uranium nitride, uranium carbide, uranium carbon oxygen, etc.
  • the material of the elastic member 2 can be nickel-based alloy, molybdenum alloy, stainless steel, aluminum alloy, zirconium alloy, etc.
  • the material of the cladding tube 3 used in conjunction with the split-petal nuclear fuel pellet structure can be zirconium alloy, SiC composite material, etc.
  • the SiC composite cladding tube fuel rod according to an embodiment of the present invention comprises the above-mentioned petal-type nuclear fuel pellet structure, a SiC composite cladding tube 30 , an air cavity spring 5 , an upper end plug 60 and a lower end plug 61 .
  • the upper end plug 60 and the lower end plug 61 are respectively connected to the upper and lower ends of the SiC composite material cladding tube 30; a plurality of petal-type nuclear fuel core block structures are stacked in sequence in the inner cavity of the SiC composite material cladding tube 30 along the axial direction of the SiC composite material cladding tube 30, and the plurality of petal-type nuclear fuel core block structures are coaxially arranged with the SiC composite material cladding tube 30; the air cavity spring 5 is arranged in the inner cavity of the SiC composite material cladding tube 30, and is connected between the petal-type nuclear fuel core block structure and the upper end plug 60.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

La présente invention concerne une structure de pastille de combustible nucléaire de type fendu, et une barre de combustible ayant une gaine en composite SiC. La structure de pastille de combustible nucléaire de type fendu comprend une pastille (1) et un élément élastique (2), une cavité (11) destinée à recevoir l'élément élastique (2) étant ménagée au milieu de la pastille (1) ; la pastille (1) comprenant au moins deux sections de pastille (10) ajustées radialement l'une à l'autre, l'élément élastique (2) étant logé dans la cavité (11) et venant buter contre les sections de pastille (10). Dans la structure de la pastille de combustible nucléaire de type fendu, la pastille (1) est étroitement ajustée à un tube de gaine de combustible nucléaire (3) sans interstices, ce qui peut assurer un transfert thermique circonférentiel uniforme de la barre de combustible. La pastille (1) ayant la cavité (11) au milieu peut réduire davantage la température maximale de fonctionnement de la pastille (1), et la cavité (11) peut contenir davantage de gaz de fission, de sorte que la pression interne de la barre de combustible peut être réduite.
PCT/CN2022/130706 2022-11-08 2022-11-08 Structure de pastille de combustible nucléaire de type fendu, et barre de combustible ayant une gaine en composite sic WO2024098261A1 (fr)

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PCT/CN2022/130706 WO2024098261A1 (fr) 2022-11-08 2022-11-08 Structure de pastille de combustible nucléaire de type fendu, et barre de combustible ayant une gaine en composite sic

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PCT/CN2022/130706 WO2024098261A1 (fr) 2022-11-08 2022-11-08 Structure de pastille de combustible nucléaire de type fendu, et barre de combustible ayant une gaine en composite sic

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EP3503119A1 (fr) * 2017-12-22 2019-06-26 Westinghouse Electric Sweden AB Unité de combustible haute densité pour un réacteur nucléaire et barre de combustible comprenant une pluralité de telles unités de combustible
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CN211319730U (zh) * 2019-12-23 2020-08-21 西南科技大学 一种弱pci效应的液态铅铋冷却ads反应堆用燃料棒
CN113161021A (zh) * 2021-04-25 2021-07-23 西安交通大学 一种快中子反应堆中空氮化铀燃料元件
WO2022223510A1 (fr) * 2021-04-19 2022-10-27 Commissariat A L'energie Atomique Et Aux Energies Alternatives Pastille de combustible nucléaire intégrant un insert métallique ou alliage métallique conducteur thermique à disques pleins et tige pleine reliant les disques selon l'axe central, crayon et assemblage de combustible nucléaire associés, utilisation en réacteur à eau sous pression (rep)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3022240A (en) * 1958-10-03 1962-02-20 Charles H Bassett Nuclear reactor fuel element
EP0132911A2 (fr) * 1983-05-06 1985-02-13 The Babcock & Wilcox Company Barres de combustible annulaires pour réacteurs nucléaires
KR20180021326A (ko) * 2016-08-19 2018-03-02 한국원자력연구원 중심부에 밀폐된 빈공간을 포함하는 핵연료 소결체 및 이를 포함하는 핵연료봉
CN110603602A (zh) * 2017-05-09 2019-12-20 西屋电气有限责任公司 具有离散可燃吸收剂销的环形核燃料芯块
EP3503119A1 (fr) * 2017-12-22 2019-06-26 Westinghouse Electric Sweden AB Unité de combustible haute densité pour un réacteur nucléaire et barre de combustible comprenant une pluralité de telles unités de combustible
CN211319730U (zh) * 2019-12-23 2020-08-21 西南科技大学 一种弱pci效应的液态铅铋冷却ads反应堆用燃料棒
WO2022223510A1 (fr) * 2021-04-19 2022-10-27 Commissariat A L'energie Atomique Et Aux Energies Alternatives Pastille de combustible nucléaire intégrant un insert métallique ou alliage métallique conducteur thermique à disques pleins et tige pleine reliant les disques selon l'axe central, crayon et assemblage de combustible nucléaire associés, utilisation en réacteur à eau sous pression (rep)
CN113161021A (zh) * 2021-04-25 2021-07-23 西安交通大学 一种快中子反应堆中空氮化铀燃料元件

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