KR101209180B1 - Reactor vessel for minimizing ecc bypass - Google Patents

Reactor vessel for minimizing ecc bypass Download PDF

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KR101209180B1
KR101209180B1 KR1020110082077A KR20110082077A KR101209180B1 KR 101209180 B1 KR101209180 B1 KR 101209180B1 KR 1020110082077 A KR1020110082077 A KR 1020110082077A KR 20110082077 A KR20110082077 A KR 20110082077A KR 101209180 B1 KR101209180 B1 KR 101209180B1
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reactor vessel
reactor
safety injection
water
flow path
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KR1020110082077A
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Korean (ko)
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이석호
유성창
유극종
강상희
송찬이
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한국수력원자력 주식회사
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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
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/086—Pressurised water reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • 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

PURPOSE: A reactor vessel with an ECC(emergency core cooling) bypass reduction function is provided to prevent an LOCA(Loss-Of-Coolant Accident) due to the separation of an installation structure by removing an additional installation structure. CONSTITUTION: A reactor vessel(100) has a preset thickness. A nozzle part(110) is installed in the reactor vessel and supplies ECC water into the reactor vessel. A flow path(111) is vertically engraved in an inner wall(101) of the reactor vessel. A transverse section of the flow path is formed with a curved surface.

Description

안전주입수 우회 저감 기능을 갖는 원자로 용기{Reactor vessel for minimizing ECC bypass}Reactor vessel for minimizing ECC bypass

본 발명은 원자로 용기에 관한 것으로, 특히 냉각재 상실사고(LOCA)를 완화하기 위하여 원자로 용기에 직접 투입되는 안전주입수의 우회율을 저감할 수 있는 원자로 용기에 관한 것이다.
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor vessel, and more particularly, to a reactor vessel capable of reducing the bypass rate of safety injection water directly injected into the reactor vessel in order to alleviate LOCA.

냉각재 상실사고(Loss-Of-Coolant Accident: LOCA)는 원자로 냉각계통에서 발생하는 사고중 하나로, 노심 냉각을 위한 냉각재의 부족을 유발시키며, 효과적인 대응이 이루어지지 않으면 노심에 커다란 충격을 줄 수 있다(노심용융 사고). 따라서, 대부분의 원자력발전소에서는 냉각재 누출사고 시에 효율적으로 대비할 수 있는 비상노심냉각장치(Emergency Core Cooling System: ECCS)를 갖추고 있다.Loss-Of-Coolant Accident (LOCA) is one of the accidents that occur in the reactor cooling system, causing a lack of coolant for core cooling, which can cause a significant impact on the core without effective response. Core meltdown accident). Therefore, most nuclear power plants are equipped with an Emergency Core Cooling System (ECCS) that can efficiently prepare for coolant leakage accidents.

정상적인 원자로는 냉각재를 이용하여 노심에서 발생된 열을 배출시키며, 그 열을 이용하여 발전을 한다. 만약 냉각재가 부족하거나 없어져 버리면 원자로 비상 정지(scram)가 발동하여 연쇄반응을 중단시킨다. 그러나 연료의 방사능 붕괴열로 인하여 일정량의 열이 원자로에 남게 되며, 이때 ECCS가 설계대로 작동되지 않는 경우에 원자로는 큰 손상을 입게 된다.Normal reactors use coolant to release heat generated from the core and generate power using that heat. If the coolant runs out or disappears, a reactor scram is triggered to stop the chain reaction. However, due to the heat of radiation decay of the fuel, a certain amount of heat remains in the reactor, which can cause significant damage if the ECCS is not working as designed.

이와 같이 냉각수의 원활한 공급이 이루어지지 않거나 냉각수의 누수가 발생하는 경우에는 원자로 노심의 과열로 인하여 원자로가 소손되는 중대사고로 진행될 수 있다.In this case, when the supply of the coolant is not smoothly performed or leaks of the coolant occur, the reactor may be damaged due to overheating of the reactor core.

따라서, 냉각수 누수와 같이 냉각수 공급에 문제가 발생하는 경우에 안전주입수를 외부로부터 원자로 용기 내에 공급하도록 하는 방식이 사용되며, 이러한 방식으로는 주입노즐이 저온관에 연결된 주입관을 통해 안전주입수를 원자로에 주입하는 저온관 주입방식과 원자로 용기에 직접 안전주입수를 주입하게 되는 원자로 용기 직접주입 방식이 있다.Therefore, in the event of a problem in cooling water supply, such as cooling water leakage, a method of supplying safety injection water from the outside into the reactor vessel is used. There is a low temperature tube injection method for injecting the reactor into the reactor and a reactor container direct injection method for injecting the safety injection water directly into the reactor vessel.

그러나, 저온관 주입방식에서는 파단된 저온관에 안전주입수를 공급하는 경우에 파단 부위로 안전주입수가 누출되어 원자로 노심냉각 효과를 기대하기 힘들며, 따라서 현재는 원자로 용기에 안전주입수를 직접 공급하는 직접주입(Direct Vessel Injection nozzle: DVI) 방식을 채택하는 추세이다.
However, in the low temperature pipe injection method, when the safety injection water is supplied to the broken low temperature pipe, the safety injection water leaks to the fracture site, so it is difficult to expect the core cooling effect of the reactor. Therefore, the safety injection water is currently directly supplied to the reactor vessel. Direct Vessel Injection nozzle (DVI) is the trend to adopt.

도 1은 일반적인 가압 경수로형 원자로 용기의 개략적 구조를 보여주는 종단면도로서, 원자로 용기(10) 내에는 노심배럴(20)이 설치되며, 노심배럴(20)에는 핵연료봉이 장입되는 노심(21)이 위치한다. 도면부호 13은 원자로 용기(10)와 노심배럴(20) 사이 형성된 공간인 강수부이다.1 is a longitudinal cross-sectional view showing a schematic structure of a general pressurized water reactor reactor vessel, the core barrel 20 is installed in the reactor vessel 10, the core barrel 20 is the core 21 is loaded with the nuclear fuel rod is located do. Reference numeral 13 denotes a precipitation portion, which is a space formed between the reactor vessel 10 and the core barrel 20.

원자로 용기(10)는 원자로 냉각수가 순환 공급되는 저온관(11)이 구비되며 노심배럴(20)에는 고온관(미도시)에 연결되어, 저온관(11)을 통해 유입된 냉각수는 강수부(13)를 거쳐 노심(21)을 지나 고온관을 통해 증기발생기 측으로 배출된다.The reactor vessel 10 is provided with a low temperature tube 11 for circulating and supplying the reactor coolant, and the core barrel 20 is connected to a high temperature tube (not shown), and the coolant introduced through the low temperature tube 11 is a precipitation part ( 13) is passed through the core 21 and is discharged to the steam generator side through a hot tube.

또한 원자로 용기(10)는 직접주입노즐(12)이 마련되어 저온관(11)이 파단되는 등의 비상 냉각 상황에서 직접주입노즐(12)을 통하여 안전주입수가 원자로 용기(10) 내로 주입된다.In addition, in the reactor vessel 10, the safety injection water is injected into the reactor vessel 10 through the direct injection nozzle 12 in an emergency cooling situation in which the direct injection nozzle 12 is provided and the low temperature pipe 11 is broken.

그러나, 이러한 종래의 직접주입 방식의 원자로 용기는 저온관(11)과 인접하여 직접주입노즐(12)이 구비되므로 직접주입노즐(12)을 통해 주입된 안전주입수가 노심 냉각에 기여하지 못하고 파단 저온관(11)으로 우회하여 안전주입수가 유출될 수 있다.However, since such a conventional direct injection reactor vessel is provided with a direct injection nozzle 12 adjacent to the low temperature pipe 11, the safety injection water injected through the direct injection nozzle 12 does not contribute to the core cooling and breaks low temperature. By bypassing the pipe (11) can be leaked safety injections.

종래기술로는 안전주입수의 우회율 저감을 위하여 원자로 용기 내벽이나 노심배럴 측에 안전주입수를 안내하는 안내관, 덕트 또는 디플렉터(deflector)를 설치하여 안전주입수의 원활한 노심 유입을 유도하고 있다[참고문헌: 공개특허 제10-2005-0022414호(공개일자: 2005.03.08), 공개특허 제10-2009-99194호(공개일자: 2009.09.22.)].In the prior art, a guide pipe, a duct or a deflector for guiding the safety injection is installed on the inner wall of the reactor vessel or the core barrel to reduce the bypass rate of the safety injection. [Ref. Patent Publication No. 10-2005-0022414 (published: 2005.03.08), Publication No. 10-2009-99194 (published: 2009.09.22.)].

그러나, 이러한 종래기술은 원자로 용기의 강수부(13)의 틈이 좁기 때문에 안내관이나 덕트와 같은 돌출된 구조물의 설치가 상당히 어려우며, 또한 원자로 용기와 노심배럴의 조립 시에 이러한 돌출된 구조물에 의한 간섭이 발생할 수가 있다.
However, this prior art makes installation of protruding structures such as guide tubes or ducts very difficult because the gap of the precipitation section 13 of the reactor vessel is narrow, and also due to the projecting structure of the reactor vessel and the core barrel. Interference may occur.

본 발명은 이러한 종래의 문제점을 해결하기 위한 것으로, 냉각재 상실사고(LOCA)를 완화하기 위하여 원자로 용기에 투입되는 안전주입수의 우회율을 저감하도록 하며, 특히 강수부에 별도의 돌출된 구조물을 갖지 않는 원자로 용기를 제공하고자 하는 것이다.
The present invention is to solve such a conventional problem, to reduce the bypass rate of the safety injection water injected into the reactor vessel in order to alleviate the loss of coolant (LOCA), in particular having a separate protruding structure in the precipitation section Is to provide a reactor vessel.

본 발명의 원자로 용기는 안전주입수를 원자로 용기에 직접 주입하게 되는 가압 경수로형 원자로 용기에 있어서, 상기 원자로 용기의 내벽면에 음각 형성된 유로와 연통되어 상기 원자로 용기 내부로 안전주입수를 공급하기 위한 노즐부에 의해 제공될 수 있다.
The reactor vessel of the present invention is a pressurized light-water reactor type reactor that injects safety injection water directly into the reactor vessel, in communication with the flow path formed intaglio on the inner wall surface of the reactor vessel for supplying the safety injection water into the reactor vessel It can be provided by the nozzle portion.

본 발명에 따른 원자로 용기는 원자로 용기의 내벽면에 음각 형성된 유로와 연통되어 안전주입수를 공급하기 위한 노즐부가 구비됨으로써, 안전주입수 우회 저감을 위하여 강수부에 별도의 돌출된 구조물을 갖지 않으며, 또한 별도의 설치물을 필요로 하지 않으므로 설치물 이탈에 의한 사고요인을 근본적으로 제거하여 냉각재 상실사고의 완화 및 추가적인 사고요인을 사전에 예방할 수 있는 탁월한 효과가 있다.
The reactor vessel according to the present invention is provided with a nozzle portion for supplying the safety injection water in communication with the intaglio formed on the inner wall surface of the reactor vessel, it does not have a separate protruding structure in the precipitation portion to reduce the safety injection water bypass, In addition, since there is no need for a separate installation, there is an excellent effect of fundamentally eliminating accident factors due to installation deviations to alleviate the loss of coolant and to prevent additional accidents in advance.

도 1은 일반적인 가압 경수로형 원자로 용기의 개략적 구조를 보여주는 종단면도,
도 2는 본 발명에 따른 원자로 용기의 요부 구성을 보여주는 도면,
도 3은 도 2의 A-A 선의 단면도,
도 4는 도 3의 B-B 선의 단면도.
1 is a longitudinal sectional view showing a schematic structure of a general pressurized water reactor reactor vessel;
2 is a view showing the main configuration of the reactor vessel according to the present invention,
3 is a cross-sectional view taken along the line AA of FIG.
4 is a cross-sectional view taken along line BB of FIG. 3.

이하, 본 발명의 실시예를 첨부 도면을 참고하여 상세히 설명하면 다음과 같다.Hereinafter, embodiments of the present invention will be described in detail with reference to the accompanying drawings.

본 발명에 따른 원자로 용기는 안전주입수를 원자로 용기에 직접 주입하게 되는 가압 경수로형 원자로 용기에 있어서, 상기 원자로 용기(100)의 내벽면(101)에 음각 형성된 유로(111)와 연통되어 상기 원자로 용기(100) 내부로 안전주입수를 공급하기 위한 노즐부(110)가 구비되는 것을 특징으로 한다.
The reactor vessel according to the present invention is a pressurized light-water reactor reactor in which the safety injection water is injected directly into the reactor vessel, the reactor is in communication with the flow path 111 formed intaglio on the inner wall surface 101 of the reactor vessel 100 The nozzle unit 110 for supplying the safety injection water into the container 100 is characterized in that it is provided.

일정한 두께를 갖는 원자로 용기(100)의 내벽면(101)에는 대체로 수직하게 유로(111)가 음각 형성되며, 유로(111)의 상단에는 안전주입수가 주입되는 노즐부(110)가 연통된다.The inner wall surface 101 of the reactor vessel 100 having a constant thickness is generally intaglio is formed vertically, the nozzle portion 110 is injected into the upper end of the flow path 111 is injected safety injection.

노즐부(110)에는 안전주입수를 원자로 용기 내부로 직접 주입하기 위하여 주지의 주입펌프와 주입탱크가 연결될 수 있다.The nozzle 110 may be connected to a well-known injection pump and an injection tank in order to directly inject the safety injection water into the reactor vessel.

이러한 노즐부와 유로는 저온관의 위치를 고려하여 원자로 용기 내에 하나 또는 다수가 마련될 수 있다.One or more of these nozzle parts and the flow path may be provided in the reactor vessel in consideration of the location of the low temperature pipe.

특히 본 발명에 있어서, 유로는 횡단면이 곡면인 것을 특징으로 한다.
In particular, in the present invention, the flow passage is characterized in that the cross section is curved.

이와 같이 구성된 본 발명의 원자로 용기는 안전주입 작동 시에 노즐부(110)를 통해 주입된 안전주입수가 원자로 용기 내벽면에 음각 형성된 유로(111)를 따라서 증기의 영향 없이 원자로 용기 하부로 유입되어 노심 냉각이 이루어질 수가 있다.
In the reactor vessel of the present invention configured as described above, the safety injection water injected through the nozzle unit 110 during the safety injection operation is introduced into the reactor vessel bottom without the influence of steam along the flow path 111 formed on the inner wall of the reactor vessel. Cooling can be achieved.

이상에서 설명한 본 발명은 전술한 실시예 및 첨부된 도면에 의해 한정되는 것이 아니고, 본 발명의 기술적 사상을 벗어나지 않는 범위 내에서 여러 가지 치환, 변형 및 변경이 가능함은 본 발명이 속하는 기술분야에서 통상의 지식을 가진 자에게 명백할 것이다.
The present invention described above is not limited to the above-described embodiment and the accompanying drawings, and various substitutions, modifications, and changes are possible within the scope without departing from the technical spirit of the present invention. It will be evident to those who have knowledge of.

100 : 원자로 용기 110 : 노즐부
111 : 유로100: reactor vessel 110: nozzle portion
111: Euro

Claims (2)

안전주입수를 원자로 용기에 직접 주입하게 되는 가압 경수로형 원자로 용기에 있어서,
상기 원자로 용기 내부로 안전주입수를 공급하기 위한 노즐부가 구비되되, 상기 원자로 용기의 내벽면에는 상기 노즐부의 내측 개구부와 연결되어 직하방으로 수직하게 음각 형성된 유로가 형성되는 것을 특징으로 하는 원자로 용기.In a pressurized water reactor reactor vessel in which safety injection water is injected directly into the reactor vessel,
And a nozzle unit for supplying safety injection water into the reactor vessel, wherein an inner wall surface of the reactor vessel is connected to an inner opening of the nozzle portion to form a recess formed vertically downwardly. 제1항에 있어서, 상기 유로는 횡단면이 곡면인 것을 특징으로 하는 원자로용기.The reactor vessel of claim 1, wherein the flow path is curved in cross section.
KR1020110082077A 2011-08-18 2011-08-18 Reactor vessel for minimizing ecc bypass KR101209180B1 (en)

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CN114664464A (en) * 2022-02-28 2022-06-24 深圳中广核工程设计有限公司 Guiding device for reactor and reactor

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KR101082061B1 (en) 2010-05-13 2011-11-10 한국원자력연구원 Large power reactor

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KR101082061B1 (en) 2010-05-13 2011-11-10 한국원자력연구원 Large power reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114664464A (en) * 2022-02-28 2022-06-24 深圳中广核工程设计有限公司 Guiding device for reactor and reactor

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