WO2025155154A1 - Grille d'espacement hybride - Google Patents

Grille d'espacement hybride

Info

Publication number
WO2025155154A1
WO2025155154A1 PCT/KR2025/099031 KR2025099031W WO2025155154A1 WO 2025155154 A1 WO2025155154 A1 WO 2025155154A1 KR 2025099031 W KR2025099031 W KR 2025099031W WO 2025155154 A1 WO2025155154 A1 WO 2025155154A1
Authority
WO
WIPO (PCT)
Prior art keywords
mixing
support grid
hybrid support
grid
nuclear fuel
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
PCT/KR2025/099031
Other languages
English (en)
Korean (ko)
Inventor
방인철
김현지
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
UNIST Academy Industry Research Corp
Original Assignee
UNIST Academy Industry Research Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Priority claimed from KR1020250005481A external-priority patent/KR20250112700A/ko
Application filed by UNIST Academy Industry Research Corp filed Critical UNIST Academy Industry Research Corp
Publication of WO2025155154A1 publication Critical patent/WO2025155154A1/fr
Pending legal-status Critical Current
Anticipated expiration legal-status Critical

Links

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
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34—Spacer grids
    • 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
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34—Spacer grids
    • G21C3/356—Spacer grids being provided with fuel element supporting members
    • 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 present invention relates to a hybrid support grid for enhancing turbulent mixing of coolant in a nuclear reactor.
  • the existing mixing vane support grid for nuclear fuel assemblies attaches mixing vanes to the top of the unit grid that supports the nuclear fuel rods to promote cross-flow mixing between the subchannels.
  • the flow path blockage rate and the pressure loss within the core are large, and there may be a risk of local overheating of the nuclear fuel rods due to the generation of insufficient turbulence intensity.
  • the purpose of the present invention is to provide a hybrid support grid capable of reducing the possibility of local overheating of nuclear fuel rods, thereby improving safety within a reactor core, and reducing the rate of fuel clogging that causes pressure loss within the reactor core.
  • a hybrid support grid may include a channel for mixing coolant having a bending angle formed in a region in contact with a nuclear fuel rod, and a mixing vane extending in the direction of the flow of the coolant at a height after the exit of the channel.
  • hybrid support grid may be provided in multiple numbers and arranged longitudinally and transversely to surround the nuclear fuel rod.
  • a plurality of the above hybrid support grids surrounding one nuclear fuel rod can be set as a unit grid.
  • the above-described path may have the bending angle such that the coolant rotates in one direction through the path of the hybrid support grid included in the above-described unit grid.
  • the hybrid wing may have a bending angle such that the hybrid support grids connected through different unit grid arrangements are in opposite directions.
  • the second mixing wing is formed at the end of the path in the direction of the bending angle of the path, and may have a bending angle in the same direction as the path.
  • a hybrid support grid can be provided that can reduce the possibility of local overheating of a nuclear fuel rod, thereby improving safety within the core, and achieve a reduction in the rate of fuel plugging that causes pressure loss within the core.
  • FIG. 1 is a drawing illustrating the configuration of a hybrid support grid according to one embodiment of the present invention.
  • FIG. 2 is a drawing illustrating an example of unit grid formation of a hybrid support grid according to one embodiment of the present invention.
  • FIG. 5 is a drawing comparing the turbulence intensity of a hybrid support grid according to one embodiment of the present invention and a conventional support grid.
  • FIG. 8 is a diagram illustrating a graph of factors showing the effect of a hybrid support grid according to one embodiment of the present invention.
  • the hybrid support grid (100) is one of the main components of the nuclear fuel assembly structure and refers to a support grid that supports nuclear fuel rods. Referring to FIGS. 1 and 2, a path (120) may be provided for mixing coolant, and a bending angle may be formed in an area in contact with the nuclear fuel rod (10).
  • the flow path (120) formed in each of the hybrid support grids (100) may have a bending angle so that the coolant rotates in one direction through the flow path (120) of the hybrid support grid (100) included in the unit grid.
  • the coolant may flow crosswise in the direction of the arrow in FIG. 2.
  • the mixing wing (110) may have a bending angle so that the hybrid support grids connected through different unit grid arrangements are in opposite directions.
  • the mixing wing of the hybrid support grid belonging to the a unit grid and the mixing wing of the hybrid support grid belonging to the b unit grid may have bending angles in opposite directions.
  • Figure 4 shows the results of a computational fluid analysis of the effects of a design with a mixing channel (blue, red, black) and a conventional grid design with mixing vanes (green) on the pressure drop that occurs as the coolant flows.
  • the graph in Figure 4 shows the pressure drop versus (axial height/hydraulic diameter of the subchannel).
  • a higher turbulence intensity (T) can be generated when the euro is used compared to when the conventional mixing vane design is used, and in particular, the highest turbulence intensity generation can be confirmed in the second mixing vane.
  • T turbulence intensity
  • the hybrid support grid of the present invention can reduce crud that can be deposited on the nuclear fuel surface and impose additional thermal resistance on the nuclear fuel, since the momentum of crud erosion is the turbulence intensity.
  • FIG. 6 is a drawing illustrating a contour of a nuclear fuel wall surface of a hybrid support grid according to one embodiment of the present invention
  • FIG. 7 is a drawing illustrating a contour of a nuclear fuel surface temperature of a hybrid support grid according to one embodiment of the present invention.
  • the maximum nuclear fuel surface temperature was highest at approximately 603 K in the case of the conventional mixing vane, and the maximum nuclear fuel surface temperature was approximately 594 K when only the flow path was used, 596 K when the first mixing vane was used, and 591 K when the second mixing vane was used, proving that using the second mixing vane is most advantageous in securing safety in terms of the maximum nuclear fuel surface temperature.
  • FIG. 8 is a diagram illustrating a graph of factors showing the effect of a hybrid support grid according to one embodiment of the present invention.
  • the heat transfer performance between the coolant and the nuclear fuel rod can be improved by the bending angle of the flow path (120), and even if the mixing blade is located at the top of the flow path and has a small volume, the insufficient degree of cross-flow mixing can be supplemented.
  • the pressure loss can be reduced by reducing the blockage rate of the auxiliary channel by the hybrid support grid (100), thereby securing the corresponding economic efficiency.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

Une grille d'espacement hybride selon un mode de réalisation de la présente invention comprend : un trajet d'écoulement pour mélanger un fluide de refroidissement ayant un angle de courbure formé dans une région en contact avec une tige de combustible nucléaire ; et une aube de mélange s'étendant dans la direction d'écoulement du liquide de refroidissement à une hauteur en aval de la sortie du trajet d'écoulement.
PCT/KR2025/099031 2024-01-17 2025-01-16 Grille d'espacement hybride Pending WO2025155154A1 (fr)

Applications Claiming Priority (4)

Application Number Priority Date Filing Date Title
KR20240007273 2024-01-17
KR10-2024-0007273 2024-01-17
KR10-2025-0005481 2025-01-14
KR1020250005481A KR20250112700A (ko) 2024-01-17 2025-01-14 하이브리드 지지격자

Publications (1)

Publication Number Publication Date
WO2025155154A1 true WO2025155154A1 (fr) 2025-07-24

Family

ID=96471815

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/KR2025/099031 Pending WO2025155154A1 (fr) 2024-01-17 2025-01-16 Grille d'espacement hybride

Country Status (1)

Country Link
WO (1) WO2025155154A1 (fr)

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE20112336U1 (de) * 2001-07-26 2001-10-11 Framatome ANP GmbH, 91058 Erlangen Abstandhalter eines Brennelements
KR100763726B1 (ko) * 2003-03-06 2007-10-04 아레바 엔피 게엠베하 스페이서
JP2009092416A (ja) * 2007-10-04 2009-04-30 Global Nuclear Fuel-Japan Co Ltd 燃料スペーサ及び燃料集合体並びに原子炉炉心
KR101017318B1 (ko) * 2008-12-26 2011-02-28 한전원자력연료 주식회사 수력적 균형을 이루는 혼합날개 패턴을 가진 지지격자
CN202948731U (zh) * 2012-12-20 2013-05-22 中国核动力研究设计院 用于核燃料组件中具有交混性能的定位格架

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE20112336U1 (de) * 2001-07-26 2001-10-11 Framatome ANP GmbH, 91058 Erlangen Abstandhalter eines Brennelements
KR100763726B1 (ko) * 2003-03-06 2007-10-04 아레바 엔피 게엠베하 스페이서
JP2009092416A (ja) * 2007-10-04 2009-04-30 Global Nuclear Fuel-Japan Co Ltd 燃料スペーサ及び燃料集合体並びに原子炉炉心
KR101017318B1 (ko) * 2008-12-26 2011-02-28 한전원자력연료 주식회사 수력적 균형을 이루는 혼합날개 패턴을 가진 지지격자
CN202948731U (zh) * 2012-12-20 2013-05-22 中国核动力研究设计院 用于核燃料组件中具有交混性能的定位格架

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