JP2013002877A - Cooling system for reactor container - Google Patents

Cooling system for reactor container Download PDF

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JP2013002877A
JP2013002877A JP2011132385A JP2011132385A JP2013002877A JP 2013002877 A JP2013002877 A JP 2013002877A JP 2011132385 A JP2011132385 A JP 2011132385A JP 2011132385 A JP2011132385 A JP 2011132385A JP 2013002877 A JP2013002877 A JP 2013002877A
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containment vessel
reactor containment
steel plate
concrete
cooling apparatus
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Yasuki Kitajima
靖己 北島
Mitsuo Komuro
三男 小室
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Toshiba Corp
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Toshiba Corp
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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Abstract

PROBLEM TO BE SOLVED: To cool down the inside of a reactor container, steel plates and concrete constituting the container by discharging heat within the container to the outside while maintaining air-tightness inside the container in the reactor container of a steel plate/concrete structure.SOLUTION: In a cooling system for a reactor container where a gap between an inner steel plate 1a and an outer steel plate 1b is filled with concrete 2, an internal outer circumferential surface 4a and an external outer circumferential surface 4b of an annular vessel 4 in which a cooling material 5 is stored, are brought into contact with the inner steel plate 1a and the outer steel plate 1b, respectively.

Description

本発明は事故時に原子炉格納容器を冷却するための冷却装置に関する。   The present invention relates to a cooling device for cooling a reactor containment vessel in the event of an accident.

近年、原子力発電所において、事故時に外部への放射性物質の放出を防ぐために、鉄筋コンクリート製の原子炉格納容器が使用されている。このような格納容器として、内面を鋼製ライナで内張りした鉄筋コンクリート構造や内側及び外側にスタッド付き鋼板を配置し、内部にコンクリート部を挟み込んだ鉄筋部を有しない鋼板コンクリート構造か提案されている(特許文献1)。この鋼板コンクリート構造は、内側鋼板と外側鋼板からなる一対の鋼板と、各鋼板の内面に設けられた複数のスタットボルトと、一対の鋼板の間に充填されたコンクリート部から構成される(図2参照)。   In recent years, nuclear power plants have used nuclear reactor containment vessels made of reinforced concrete to prevent the release of radioactive materials to the outside in the event of an accident. As such a containment vessel, a reinforced concrete structure with an inner surface lined with a steel liner or a steel plate concrete structure in which a steel plate with studs is arranged on the inside and outside, and no reinforcing bar portion with a concrete portion sandwiched therein is proposed ( Patent Document 1). The steel plate concrete structure is composed of a pair of steel plates composed of an inner steel plate and an outer steel plate, a plurality of stat bolts provided on the inner surface of each steel plate, and a concrete portion filled between the pair of steel plates (FIG. 2). reference).

このような鋼板コンクリート構造の原子炉格納容器は、現場で鉄筋部を組立て・建造する必要がないため、工期期間を短縮することができるとともに、内側鋼板が従来の鋼板ライナの代替構造となることで原子炉格納容器内の機密性を確保し、放射性物質の放出を防止する機能を有している。   Such a steel-concrete reactor containment vessel does not require assembling and building rebars on site, so the construction period can be shortened and the inner steel plate can be an alternative to the conventional steel plate liner. Therefore, it has the function of ensuring the confidentiality in the reactor containment vessel and preventing the release of radioactive materials.

一方、電源喪失事故等の苛酷事故時において、原子炉の冷却機能が失われたり、原子炉格納容器内に高温の蒸気等が放出されたりすると、原子炉格納容器内が高温となり、最悪の場合、原子炉格納容器の機密性が失われる恐れがある。そのために、従来の原子炉格納容器では、格納容器が高温になるのを防止するために、原子炉格納容器の外周壁に冷却水又は冷却空気を散布して冷却する手段、原子炉格納容器の一部を熱伝導度の高い鋼材等で形成し原子炉格納容器内の熱を外部へ放出する手段(特許文献2)、原子炉格納容器のコンクリート内部に冷却管を配設することにより原子炉格納容器が高温になるのを防止する手段(特許文献3)等が提案されている。   On the other hand, in the worst case, if the reactor cooling function is lost or high-temperature steam is released into the reactor containment in a severe accident such as a power loss accident, the reactor containment becomes hot. The confidentiality of the containment vessel may be lost. Therefore, in the conventional reactor containment vessel, in order to prevent the containment vessel from becoming high temperature, means for spraying cooling water or cooling air on the outer peripheral wall of the reactor containment vessel and cooling the reactor containment vessel, Reactor by forming a part of steel material with high thermal conductivity and releasing the heat in the reactor containment vessel (Patent Document 2), and by installing a cooling pipe inside the concrete of the containment vessel Means (Patent Document 3) and the like for preventing the containment vessel from becoming high temperature have been proposed.

特許第3309290号公報Japanese Patent No. 3309290 特開平11−84056号公報Japanese Patent Laid-Open No. 11-84056 特開2005−189043号公報JP 2005-189043 A

従来の鋼板又は鋼製ライナを用いた原子炉格納容器は内側鋼板と外側鋼板の間にコンクリートを充填した構造となっているが、コンクリートは高温状態では内部の水分が蒸散し、強度低下が発生する懸念があり、また、コンクリート自体の熱伝達率が低いため、原子炉格納容器内部が高温となる事故時に内側の鋼製ライナや鋼板が熱により座屈変形し、鋼製ライナや鋼板とコンクリートとの間に空隙が発生する可能性があり、その際、熱伝達性能はさらに悪化する可能性がある。   Conventional reactor containment vessels using steel plates or steel liners have a structure in which concrete is filled between the inner and outer steel plates, but the concrete loses strength due to evaporation of internal moisture at high temperatures. In addition, because the heat transfer coefficient of the concrete itself is low, the inner steel liner and the steel plate are buckled and deformed due to heat in the event of a high temperature inside the reactor containment vessel. There is a possibility that voids are generated between the two and the heat transfer performance may be further deteriorated.

一方、原子炉格納容器内の熱を外部へ逃がすために、冷却水プールの壁面となる原子炉格納容器の一部を高熱伝導の材料で形成したり(特許文献2)、原子炉格納容器床面のコンクリート部に冷却管を埋設すること(特許文献3)が提案されているが、これらの除熱手段は、原子炉格納容器内の局所的な高温発生部の熱を外部に逃すためのもので、原子炉格納容器を構成する鋼板及びコンクリート自体を冷却する機能は有していない。このように、従来の原子炉格納容器の冷却手段は、局部的なもので、除熱能力も小さく、原子炉格納容器を構成する鋼板及びコンクリートを全体にわたって冷却することは困難であった。   On the other hand, in order to release the heat in the reactor containment vessel to the outside, a part of the reactor containment vessel that becomes the wall surface of the cooling water pool is formed of a material having high thermal conductivity (Patent Document 2), or the reactor containment vessel floor Although it has been proposed to embed a cooling pipe in the concrete part of the surface (Patent Document 3), these heat removal means are used to release the heat of the local high temperature generating part in the reactor containment vessel to the outside. However, it does not have a function of cooling the steel plate and concrete itself constituting the reactor containment vessel. Thus, the conventional reactor containment vessel cooling means is local, has a small heat removal capability, and it has been difficult to cool the steel plate and concrete constituting the reactor containment vessel as a whole.

本発明は上記課題を解決するためになされたものであり、鋼板コンクリート構造の原子炉格納容器において、格納容器内部の気密性を保持したまま格納容器内部の熱を外部へ放出することにより、原子炉格納容器内並びに格納容器を構成する鋼板及びコンクリートを冷却することができる原子炉格納容器の冷却装置を提供することを目的とする。   The present invention has been made to solve the above problems, and in a nuclear reactor containment of a steel plate concrete structure, by releasing heat inside the containment vessel while maintaining the airtightness inside the containment vessel, It is an object of the present invention to provide a reactor containment vessel cooling apparatus capable of cooling the inside of the reactor containment vessel and the steel plates and concrete constituting the containment vessel.

上述した課題を解決するために、本発明に係る原子炉格納容器の冷却装置は、内側鋼板と外側鋼板との間にコンクリートが充填された原子炉格納容器の冷却装置において、内部に冷却材が収容された環状容器の内側外周面と外側外周面を前記内側鋼板と外側鋼板にそれぞれ接触させたことを特徴とする。   In order to solve the above-described problems, a reactor containment vessel cooling apparatus according to the present invention is a reactor containment vessel cooling apparatus in which concrete is filled between an inner steel plate and an outer steel plate. The inner and outer peripheral surfaces of the annular container accommodated are brought into contact with the inner and outer steel plates, respectively.

また、本発明に係る原子炉格納容器の冷却装置は、内側鋼板と外側鋼板との間にコンクリートが充填された原子炉格納容器の冷却装置において、前記内側鋼板と外側鋼板との間のコンクリート部に設けられた複数の散水・蒸気捕集配管と、各散水・蒸気捕集管に設けられた複数の開口と、各散水・蒸気捕集配管の下部に配管を介して接続されたドレンタンクとを有することを特徴とする。   The reactor containment vessel cooling device according to the present invention is a reactor containment vessel cooling device in which concrete is filled between an inner steel plate and an outer steel plate, and a concrete portion between the inner steel plate and the outer steel plate. A plurality of water sprinkling / steam collecting pipes provided in the water, a plurality of openings provided in each water sprinkling / steam collecting pipe, and a drain tank connected to the lower part of each water sprinkling / steam collecting pipe via a pipe; It is characterized by having.

本発明によれば、苛酷事故時等において、原子炉格納容器内部の気密性を保持したまま格納容器内部の熱を外部へ放出することにより、原子炉格納容器内並びに格納容器を構成する鋼板及びコンクリートを効率的に冷却することができる。   According to the present invention, in a severe accident or the like, by releasing the heat inside the containment vessel to the outside while maintaining the airtightness inside the containment vessel, the steel plates constituting the containment vessel and the containment vessel, and Concrete can be cooled efficiently.

第1の実施形態に係る冷却装置を備えた原子炉格納容器の模式図。The schematic diagram of the nuclear reactor containment vessel provided with the cooling device which concerns on 1st Embodiment. 第1の実施形態に係る冷却装置の断面図。Sectional drawing of the cooling device which concerns on 1st Embodiment. 第2の実施形態に係る冷却装置を備えた原子炉格納容器の全体構成図。The whole block diagram of the nuclear reactor containment vessel provided with the cooling device which concerns on 2nd Embodiment.

以下、本発明に係る原子炉格納容器の冷却装置の実施形態について、図面を参照して説明する。   Hereinafter, an embodiment of a reactor containment vessel cooling apparatus according to the present invention will be described with reference to the drawings.

(第1の実施形態)
第1の実施形態に係る原子炉格納容器の冷却装置を図1及び図2により説明する。
図1は本実施形態に係る冷却装置が配置された原子炉格納容器1の模式図であり、複数のリブ3を有する内側鋼板1a及び外側鋼板1bと、その間に充填されるコンクリート部2と、内側鋼板1aと外側鋼板1bの間に設置される環状容器4からなる冷却装置とから構成される。
(First embodiment)
A reactor containment vessel cooling apparatus according to a first embodiment will be described with reference to FIGS. 1 and 2.
FIG. 1 is a schematic diagram of a reactor containment vessel 1 in which a cooling device according to the present embodiment is arranged, and an inner steel plate 1a and an outer steel plate 1b having a plurality of ribs 3, and a concrete portion 2 filled therebetween. It is comprised from the cooling device which consists of the annular container 4 installed between the inner side steel plate 1a and the outer side steel plate 1b.

環状容器4は高熱伝導性部材からなり、図2に示すように断面が略平行四辺形状であり、その内側外周面4aが内側鋼板1aに、外側外周面4bが外側鋼板1bに接するように配置され、内部には冷却材5が封入されている。また、環状容器4内の冷却材5が対流による循環流を形成するように、少なくとも外側外周面4bの上端部が内側外周面4aの上端部よりも高く位置するように構成されている。   The annular container 4 is made of a highly heat conductive member and has a substantially parallelogram shape as shown in FIG. 2 and is arranged so that the inner outer peripheral surface 4a is in contact with the inner steel plate 1a and the outer outer peripheral surface 4b is in contact with the outer steel plate 1b. The coolant 5 is enclosed inside. Moreover, it is comprised so that the upper end part of the outer peripheral surface 4b may be located higher than the upper end part of the inner outer peripheral surface 4a so that the coolant 5 in the annular container 4 forms a circulating flow by convection.

このように構成された本第1の実施形態において、内側鋼板1aからの熱は内側外周面4aを介して冷却材5に伝わり、冷却材5は対流により環状容器4内を循環することで、外側外周面4b、外側鋼板1bを介して外部に放熱される。   In the first embodiment configured as described above, heat from the inner steel plate 1a is transmitted to the coolant 5 through the inner peripheral surface 4a, and the coolant 5 circulates in the annular container 4 by convection. Heat is radiated to the outside through the outer peripheral surface 4b and the outer steel plate 1b.

本第1の実施形態によれば、原子炉格納容器内が事故等によって高温になった場合、電源、駆動機器等の動的機器を用いることなく、受動的な装置構成によって原子炉格納容器内の熱並びに格納容器を構成する鋼板及びコンクリートの熱を外部に放熱し、原子炉格納容器内及び格納容器を冷却することができる。   According to the first embodiment, when the temperature in the reactor containment vessel becomes high due to an accident or the like, the reactor containment vessel is passively configured without using dynamic devices such as a power source and a drive device. The heat of the steel plate and the concrete constituting the containment vessel and the heat of the concrete can be radiated to the outside, and the inside of the reactor containment vessel and the containment vessel can be cooled.

なお、環状容器4は、原子炉格納容器1の全体にわたって円周方向及び上下方向に複数個設けられる。また、冷却装置は平行四辺形状の環状容器4に限らず、内側と外側の側面が鋼板に接触可能であれば、楕円形等の形状であってもよく、また、円形、楕円形又は矩形のパイプ状部材から構成してもよい。   A plurality of annular vessels 4 are provided in the circumferential direction and the vertical direction over the entire reactor containment vessel 1. Further, the cooling device is not limited to the parallelogram-shaped annular container 4, and may have an oval shape or the like as long as the inner and outer side surfaces can be in contact with the steel plate. You may comprise from a pipe-shaped member.

さらに、環状容器4内に非常用又は常用の電源によって駆動するファン等の循環装置を設け(図示せず)、冷却材5の循環を促進するようにしてもよい。
また、環状容器4が設置された原子炉格納容器の外側鋼板1bの上部に雨水等の水を収容する貯蔵容器を設け(図示せず)、冷却材5の放熱時に貯蔵容器内の水を外側鋼板1b、特に環状容器4が配置された箇所近傍に散布し、冷却機能を促進するように構成してもよい。
Further, a circulation device such as a fan that is driven by an emergency or ordinary power source may be provided in the annular container 4 (not shown) to promote circulation of the coolant 5.
In addition, a storage container (not shown) for storing water such as rainwater is provided on the outer steel plate 1b of the reactor containment vessel in which the annular container 4 is installed, and the water in the storage container is discharged outside when the coolant 5 is radiated. The steel plate 1b, particularly in the vicinity of the place where the annular container 4 is disposed, may be dispersed to promote the cooling function.

(第2の実施形態)
第2の実施形態に係る原子炉格納容器の冷却装置を図3により説明する。
本実施形態では、図3に示すように、内側鋼板1aと外側鋼板1bの間のコンクリート部2に複数の散水・蒸気捕集配管6を周方向に複数配置した構成としている。
(Second Embodiment)
A reactor containment vessel cooling apparatus according to a second embodiment will be described with reference to FIG.
In the present embodiment, as shown in FIG. 3, a plurality of sprinkling / steam collecting pipes 6 are arranged in the circumferential direction in the concrete portion 2 between the inner steel plate 1a and the outer steel plate 1b.

各散水・蒸気捕集配管6は原子炉格納容器1の側壁と略同等の高さを有し、長手方向に蒸気捕集又は散水のための開口8が複数設けられている。また、各散水・蒸気捕集配管6の上部には蒸気を貯留するための貯留部9がそれぞれ設けられ、下部は配管11を介してドレンタンク12に接続される。   Each water sprinkling / steam collecting pipe 6 has substantially the same height as the side wall of the reactor containment vessel 1, and a plurality of openings 8 for collecting or sprinkling steam are provided in the longitudinal direction. In addition, a reservoir 9 for storing steam is provided at the upper part of each water sprinkling / steam collecting pipe 6, and the lower part is connected to a drain tank 12 via a pipe 11.

このように構成された本実施形態において、事故時に原子炉格納容器1が高温になった場合、コンクリート部2で発生した蒸気は、矢印7aで示すように開口8を介して散水・蒸気捕集配管6に捕集され、コンクリート部2の内圧が上昇するのを防止するとともに、コンクリート部2が高熱により劣化するのを防止する。   In the present embodiment configured as described above, when the reactor containment vessel 1 becomes high in the event of an accident, the steam generated in the concrete part 2 is sprinkled and collected through the opening 8 as indicated by an arrow 7a. While being collected by the pipe 6, the internal pressure of the concrete part 2 is prevented from rising and the concrete part 2 is prevented from being deteriorated by high heat.

また、捕集された蒸気は貯留部9又は配管11に導かれるが、その際、蒸気は上記第1の実施形態に示す冷却装置4または自然冷却によって凝縮され、凝縮水はドレンタンク12に貯留される。   Further, the collected steam is guided to the storage unit 9 or the pipe 11. At that time, the steam is condensed by the cooling device 4 or natural cooling shown in the first embodiment, and the condensed water is stored in the drain tank 12. Is done.

一方、コンクリート部2の水分が僅少になるとコンクリート部2が高温になり強度が低下するので、ドレンタンク12からポンプ等(図示せず)によって配管11、散水・蒸気捕集配管の開口8を介して水をコンクリート部2内に散水し冷却する(矢印7b)。   On the other hand, when the moisture of the concrete part 2 becomes very low, the concrete part 2 becomes hot and the strength is lowered. Water is then sprayed into the concrete part 2 and cooled (arrow 7b).

このように散水・蒸気捕集配管6は散水及び蒸気捕集機能を併せ持ち、コンクリート部の状態に応じて、コンクリート部2からの蒸気捕集又は散水をおこなう。
また、鋼製コンクリート構造の補強のために、各散水・蒸気捕集配管6の外面にスタット又はリブを設け、散水・蒸気捕集配管を構造材として用いてもよい。
Thus, the sprinkling / steam collecting pipe 6 has both water sprinkling and steam collecting functions, and collects or sprinkles steam from the concrete part 2 according to the state of the concrete part.
Further, in order to reinforce the steel concrete structure, a stat or a rib may be provided on the outer surface of each water sprinkling / steam collecting pipe 6, and the water sprinkling / steam collecting pipe may be used as a structural material.

以上説明したよう、本実施形態によれば、コンクリート部が事故等によって高温になった場合、散水・蒸気捕集配管により適時蒸気捕集又は散水をおこなうことにより、コンクリート部の内圧上昇による破損、劣化及び強度低下を防止することができる。また、捕集した蒸気をドレンタンクに貯留し、散水冷却水として有効に活用することができる。   As described above, according to the present embodiment, when the concrete part becomes hot due to an accident or the like, damage due to an increase in internal pressure of the concrete part by performing timely steam collection or water spraying with water sprinkling / steam collecting piping, Deterioration and strength reduction can be prevented. Moreover, the collected steam can be stored in a drain tank and effectively used as sprinkling cooling water.

なお、上記実施形態では、散水・蒸気捕集管6は散水及び蒸気捕集機能を併せ持つが、散水管と蒸気捕集管を別系統とし、それぞれ原子炉格納容器1のコンクリート部2に複数配置するようにしてもよい。その際、散水管と蒸気捕集管は系統が異なる配管でドレンタンク12に接続されるか、又は各管と配管11の間に開閉弁(図示せず)を設置して、開閉弁を操作することにより散水又は蒸気捕集操作を実施してもよい。
また、ドレンタンク12には蒸気凝縮水のみならず、雨水等外部からの水を貯留するようにしてもよい。
In the above embodiment, the water sprinkling / steam collecting pipe 6 has both water sprinkling and steam collecting functions. However, the water sprinkling pipe and the steam collecting pipe are separated from each other, and a plurality of them are arranged in the concrete portion 2 of the reactor containment vessel 1 respectively. You may make it do. At that time, the sprinkler pipe and the steam collecting pipe are connected to the drain tank 12 by pipes having different systems, or an on-off valve (not shown) is installed between each pipe and the pipe 11 to operate the on-off valve. By doing so, water spraying or steam collecting operation may be performed.
Further, the drain tank 12 may store not only steam condensed water but also water from the outside such as rain water.

以上、本発明のいくつかの実施形態を説明したが、これらの実施形態は、例として提示したものであり、発明の範囲を限定することは意図していない。これら新規な実施形態は、その他の様々な形態で実施されることが可能であり、発明の要旨を逸脱しない範囲で、種々の省略、組み合わせ、置き換え、変更を行うことができる。これら実施形態やその変形は、発明の範囲や要旨に含まれるとともに、特許請求の範囲に記載された発明とその均等の範囲に含まれる。   As mentioned above, although several embodiment of this invention was described, these embodiment is shown as an example and is not intending limiting the range of invention. These novel embodiments can be implemented in various other forms, and various omissions, combinations, replacements, and changes can be made without departing from the scope of the invention. These embodiments and modifications thereof are included in the scope and gist of the invention, and are included in the invention described in the claims and the equivalents thereof.

1…原子炉格納容器、1a…内側鋼板、1b…外側鋼板、2…コンクリート部、3…スタッド、4…環状容器、4a…内側外周面、4b…外側外周面、5…冷却材、6…散水・蒸気捕集配管、8…開口、9…貯留部、10…原子炉圧力容器、11…配管、12…ドレンタンク。   DESCRIPTION OF SYMBOLS 1 ... Reactor containment vessel, 1a ... Inner steel plate, 1b ... Outer steel plate, 2 ... Concrete part, 3 ... Stud, 4 ... Ring container, 4a ... Inner outer peripheral surface, 4b ... Outer outer peripheral surface, 5 ... Coolant, 6 ... Sprinkling / steam collecting piping, 8 ... opening, 9 ... reservoir, 10 ... reactor pressure vessel, 11 ... piping, 12 ... drain tank.

Claims (8)

内側鋼板と外側鋼板との間にコンクリートが充填された原子炉格納容器の冷却装置において、
内部に冷却材が収容された環状容器の内側外周面と外側外周面を前記内側鋼板と外側鋼板にそれぞれ接触させたことを特徴とする原子炉格納容器の冷却装置。
In the reactor containment vessel cooling device filled with concrete between the inner and outer steel plates,
A reactor containment vessel cooling apparatus, wherein an inner outer peripheral surface and an outer outer peripheral surface of an annular container having a coolant contained therein are brought into contact with the inner steel plate and the outer steel plate, respectively.
前記環状容器を原子炉格納容器の周方向及び上下方向に複数配置したことを特徴とする請求項1記載の原子炉格納容器の冷却装置。   2. The reactor containment vessel cooling apparatus according to claim 1, wherein a plurality of the annular vessels are arranged in a circumferential direction and a vertical direction of the reactor containment vessel. 前記環状容器の外側外周面の上端部が内側外周面の上端部よりも高い位置にあることを特徴とする請求項1又は2記載の原子炉格納容器の冷却装置。   3. The reactor containment vessel cooling apparatus according to claim 1, wherein an upper end portion of the outer peripheral surface of the annular vessel is located higher than an upper end portion of the inner outer peripheral surface. 前記環状容器に冷却材循環装置を設けたことを特徴とする請求項1乃至3いずれかに記載の原子炉格納容器の冷却装置。   The reactor containment vessel cooling apparatus according to any one of claims 1 to 3, wherein a coolant circulation device is provided in the annular vessel. 前記外側鋼板に冷却材を散布することを特徴とする請求項1乃至4いずれかに記載の原子炉格納容器の冷却装置。   The reactor containment vessel cooling apparatus according to claim 1, wherein a coolant is sprayed on the outer steel plate. 内側鋼板と外側鋼板との間にコンクリートが充填された原子炉格納容器の冷却装置において、
前記内側鋼板と外側鋼板との間のコンクリート部に設けられた複数の散水・蒸気捕集配管と、各散水・蒸気捕集管に設けられた複数の開口と、各散水・蒸気捕集配管の下部に配管を介して接続されたドレンタンクとを有することを特徴とする原子炉格納容器の冷却装置。
In the reactor containment vessel cooling device filled with concrete between the inner and outer steel plates,
A plurality of water spray / steam collection pipes provided in the concrete portion between the inner steel plate and the outer steel plate, a plurality of openings provided in each water spray / steam collection pipe, and each water spray / steam collection pipe A reactor containment vessel cooling apparatus comprising a drain tank connected to a lower portion via a pipe.
前記複数の散水・蒸気捕集配管の代わりに、複数の散水配管と複数の蒸気捕集配管を設けたことを特徴とする請求項6記載の原子炉格納容器の冷却装置。 7. The reactor containment vessel cooling apparatus according to claim 6, wherein a plurality of water sprinkling pipes and a plurality of steam collecting pipes are provided in place of the plurality of water sprinkling / steam collecting pipes. 前記散水・蒸気捕集配管、散水配管又は蒸気捕集配管の外面にスタット又はリブを設けたことを特徴とする請求項6又は7記載の原子炉格納容器の冷却装置。   The reactor containment vessel cooling apparatus according to claim 6 or 7, wherein a stat or a rib is provided on an outer surface of the sprinkling / steam collecting pipe, the sprinkling pipe or the steam collecting pipe.
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JP2015108571A (en) * 2013-12-05 2015-06-11 日立Geニュークリア・エナジー株式会社 Steel plate concrete structure of reactor containment vessel building, reactor containment vessel internal structure, and reactor containment vessel

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