KR960039016A - Pore structure for perforation defense in the lower half of reactor vessel - Google Patents

Pore structure for perforation defense in the lower half of reactor vessel Download PDF

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Publication number
KR960039016A
KR960039016A KR1019950008450A KR19950008450A KR960039016A KR 960039016 A KR960039016 A KR 960039016A KR 1019950008450 A KR1019950008450 A KR 1019950008450A KR 19950008450 A KR19950008450 A KR 19950008450A KR 960039016 A KR960039016 A KR 960039016A
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KR
South Korea
Prior art keywords
gap structure
reactor vessel
gap
reactor
lower half
Prior art date
Application number
KR1019950008450A
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Korean (ko)
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KR0169864B1 (en
Inventor
황일순
서균렬
정광진
Original Assignee
황일순
서균렬
정광진
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Application filed by 황일순, 서균렬, 정광진 filed Critical 황일순
Priority to KR1019950008450A priority Critical patent/KR0169864B1/en
Publication of KR960039016A publication Critical patent/KR960039016A/en
Application granted granted Critical
Publication of KR0169864B1 publication Critical patent/KR0169864B1/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/04—Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
    • 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

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  • 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

본 발명은 원자로에 관한 것으로서 특히, 원자로의 하부에 적정한 간격으로 설치되어 용융노심에 의한 급속한 원자로용기 하반부의 과열을 방지하고, 간극 구조물과 원자로용기 하반부 사이에 간극에서 일어나는 수냉각 효과를 극대화하여 원자로용기 하반부의 천공을 방지하는 간극 구조물을 구비한 원자로에 관한 것이다.The present invention relates to a nuclear reactor, in particular, is installed at an appropriate interval in the lower part of the reactor to prevent rapid overheating of the lower half of the reactor vessel by the melt core, and maximize the water cooling effect occurring in the gap between the gap structure and the lower half of the reactor vessel A reactor having a gap structure for preventing perforation of the lower half of the vessel.

본 발명의 구성은 원자로용기의 하반부에 소정간격으로 간극 구조물을 수직집합체에 용접, 나사고정, 턱받침 구조를 이용하여 지지하고 변형 억제발을 부착하여 구성된다.The structure of the present invention is constructed by supporting the gap structure to the vertical assembly at a predetermined interval in the lower half of the reactor vessel by welding, screwing, and supporting structure, and attaching a deformation suppressing foot.

본 발명의 효과는 노심의 핵연료 및 관련 구조물이 용융하여 하부로 이동(Relocation)하여 원자로용기 하반부에 축적될 경우 용융노심과 직접적인 접촉을 차단하여 급속한 원자로용기 하반부의 과열을 방지하고, 수냉각 효과를 극대화하여 원자로용기 하분부의 천공을 방지함으로써 중대사고에 대한 안전성을 확보하는 것이다.The effect of the present invention is to prevent the overheating of the lower half of the reactor vessel by preventing direct contact with the molten core when the fuel and the related structure of the core is melted and relocated to the lower portion and accumulated in the lower half of the reactor vessel, and prevents the water cooling effect By maximizing and preventing perforation of the lower part of the reactor vessel, it is to secure safety against serious accidents.

Description

원자로심 용융사고시 원자로용기 하반부 천공바어용 간극 구조물Gap structure for perforated bar in the lower half of reactor vessel

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음As this is a public information case, the full text was not included.

제1도는 가압 경수형 원자로(Pressurized Water Reactor-PWR)에 간극 구조물의 설치를 도시한 도면, 제2도는 수로직 가압 경수형 원자로(VVER형)에서 간극 구조물의 설치를 도시한 도면, 제3도는 비등 경수형 njs자로(Boiling Water Reactor-BWR)에서 간극 구조물의 설치를 도시한 도면, 제4도는 가압 중수형 원자로(Pressurized Heavy Water Reactor-CANDU형)에서 간극 구조물의 설치를 도시한 도면.FIG. 1 shows the installation of a gap structure in a pressurized water reactor (PWR), FIG. 2 shows the installation of a gap structure in a hydraulic pressurized water reactor (VVER type), and FIG. Figure 4 shows the installation of a gap structure in a boiling water reactor (BWR), Figure 4 shows the installation of a gap structure in a pressurized heavy water reactor (CANDU type).

Claims (11)

원자로에 있어서, 원자로용기 내부의 하부에 원자로용기 내면과 적정한 간극으로 설치된 간극 구조물을 구비한 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.The reactor structure, wherein the gap structure is provided in the lower portion of the reactor vessel with a gap structure provided at an appropriate gap with the inner surface of the reactor vessel. 제1항에 있어서, 상기 간극 구조물이 한개인 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.2. The gap structure of claim 1, wherein the gap structure has one gap structure. 제1항에 있어서, 상기 간극 구조물이 2개 이상의 층인 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.2. The gap structure of claim 1, wherein the gap structure is two or more layers. 제1항에 있어서, 상기 간극 구조물의 지지는 수직집합체에 용접(11)에 의한 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.2. The gap structure of claim 1, wherein the support of the gap structure is welded to a vertical assembly. 11. 제1항에 있어서, 상기 간극 구조물의 지지는 수직집합체에 대한 고정나사에 의한 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.The method of claim 1, wherein the support of the gap structure is a gap structure for the lower half of the reactor vessel perforated defense in the reactor core melt accident, characterized in that the fixing screw for the vertical assembly. 제1항에 있어서, 상기 간극 구조물의 지지는 수직집합체의 턱받침구조(10)에 의한 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.2. The gap structure of claim 1, wherein the support of the gap structure is formed by the support structure of the vertical aggregate. 10. 제1항에 있어서, 상기 간극 구조물의 지지는 간극 구조물 하면의 변형 억제발(9) 또는 별도의 지지구조물에 의한 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.2. The gap structure of claim 1, wherein the gap structure is supported by a strain suppressing foot (9) on a lower surface of the gap structure or a separate support structure. 제1항에 있어서, 간극 구조물에 복수의 유로구명이 천공되어 있고 접시형으로 굴곡된 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.The gap structure for the lower half of the reactor vessel at the time of the nuclear reactor melt melting accident, characterized in that the plurality of flow path life is perforated and bent in the gap structure. 제1항에 있어서, 간극 구조물의 냉각효과의 증대를 위하여 방열핀, 수직간극(8), 및 보호관(7)을 포함하는 것을 특징으로 하는 원자로심 용융사고시 원자로용기 하반부 천공방어용 간극 구조물.2. The gap structure of the lower half of the reactor vessel in the core of the reactor vessel during the meltdown accident according to claim 1, characterized in that it comprises a heat dissipation fin, a vertical gap (8), and a protective tube (7) to increase the cooling effect of the gap structure. 제1항에 있어서, 정상가동시 원자로 하부의 고유 유동특성을 유지하기 위하여 상단부의 간극을 적절히 조절한 것을 특징으로 하는 원로심 용융사고시 원자로용기 하반부 천공바어용 간극 구조물.2. The gap structure of the lower portion of the reactor vessel in the lower half of the reactor vessel during the melt melting accident according to claim 1, wherein the gap of the upper end is properly adjusted to maintain the inherent flow characteristics of the lower part of the reactor during normal operation. 제1항에 있어서, 상기 간극 구조물이 원자로용기의 하반부 외부에 설치된 것을 특징으로 하는 원자로심용융사고시 원자로용기 하반부 천공바어용 간극 구조물.The method of claim 1, wherein the gap structure is installed in the outer half of the reactor vessel outside of the reactor vessel, the gap structure for the perforated bar at the bottom half of the reactor vessel. ※ 참고사항 : 최초출원 내용에 의하여 공개되는 것임.※ Note: This is to be disclosed by the original application.
KR1019950008450A 1995-04-12 1995-04-12 Clearance structure for protection of puncture of the lower head of reactor on the burst of the nuclear reactor core KR0169864B1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
KR1019950008450A KR0169864B1 (en) 1995-04-12 1995-04-12 Clearance structure for protection of puncture of the lower head of reactor on the burst of the nuclear reactor core

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Application Number Priority Date Filing Date Title
KR1019950008450A KR0169864B1 (en) 1995-04-12 1995-04-12 Clearance structure for protection of puncture of the lower head of reactor on the burst of the nuclear reactor core

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KR960039016A true KR960039016A (en) 1996-11-21
KR0169864B1 KR0169864B1 (en) 1999-04-15

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115862908A (en) * 2023-01-30 2023-03-28 上海核工程研究设计院股份有限公司 Experimental device for in-pile retention basket under serious accident

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100984017B1 (en) * 2008-12-09 2010-09-28 한국수력원자력 주식회사 Inner-wall structure for protecting a reactor vessel in the event of core melting accidecnt

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115862908A (en) * 2023-01-30 2023-03-28 上海核工程研究设计院股份有限公司 Experimental device for in-pile retention basket under serious accident
CN115862908B (en) * 2023-01-30 2024-01-12 上海核工程研究设计院股份有限公司 Experimental device for in-pile retention basket under severe accident

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