JP3110901B2 - Fast breeder reactor - Google Patents

Fast breeder reactor

Info

Publication number
JP3110901B2
JP3110901B2 JP04324471A JP32447192A JP3110901B2 JP 3110901 B2 JP3110901 B2 JP 3110901B2 JP 04324471 A JP04324471 A JP 04324471A JP 32447192 A JP32447192 A JP 32447192A JP 3110901 B2 JP3110901 B2 JP 3110901B2
Authority
JP
Japan
Prior art keywords
reactor
air
reactor vessel
air flow
flow path
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.)
Expired - Lifetime
Application number
JP04324471A
Other languages
Japanese (ja)
Other versions
JPH06174884A (en
Inventor
島 亨 飯
井 重 夫 笠
村 博 中
部 禎 男 服
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.)
Toshiba Corp
Central Research Institute of Electric Power Industry
Original Assignee
Toshiba Corp
Central Research Institute of Electric Power Industry
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
Application filed by Toshiba Corp, Central Research Institute of Electric Power Industry filed Critical Toshiba Corp
Priority to JP04324471A priority Critical patent/JP3110901B2/en
Priority to US08/097,833 priority patent/US5420897A/en
Priority to FR9309410A priority patent/FR2697104B1/en
Publication of JPH06174884A publication Critical patent/JPH06174884A/en
Application granted granted Critical
Publication of JP3110901B2 publication Critical patent/JP3110901B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • 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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【産業上の利用分野】本発明は小型の高速増殖炉に係
り、特に原子炉容器を支持する原子炉支持部の過度の温
度上昇を防止する高速増殖炉に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a small-sized fast breeder reactor, and more particularly to a fast breeder reactor for preventing an excessive rise in temperature of a reactor support for supporting a reactor vessel.

【0002】[0002]

【従来の技術】一般に原子炉格納構造物に形成された炉
容器室に原子炉容器を収容し、原子炉格納構造物の壁体
中に炉容器室に原子炉容器冷却用の空気を導入する給気
ダクトを設け、この給気ダクトのやや上方位置に原子炉
容器を冷却した高温の空気を排出する排気ダクトを設
け、この給気ダクトと排気ダクトの間に長い空気流路を
形成する炉容器空冷筒を設け、炉容器空冷筒が形成した
空気流路に冷却用空気を流通させて原子炉容器を冷却す
るようにした高速増殖炉が知られている。
2. Description of the Related Art Generally, a reactor vessel is accommodated in a reactor vessel room formed in a reactor containment structure, and air for cooling the reactor vessel is introduced into the reactor vessel room into a wall of the reactor containment structure. A furnace that has an air supply duct, and an exhaust duct that is located slightly above the air supply duct to discharge high-temperature air that has cooled the reactor vessel, and that forms a long air flow path between the air supply duct and the exhaust duct 2. Description of the Related Art A fast breeder reactor is known in which a vessel air cooling cylinder is provided, and cooling air is circulated through an air flow path formed by the reactor vessel air cooling cylinder to cool the reactor vessel.

【0003】図4は従来の高速増殖炉の構成を示してい
る。従来の高速増殖炉21は原子炉容器22を有し、こ
の原子炉容器22はコンクリートによって構築された原
子炉格納構造物23の内部に収容されている。原子炉格
納構造物23の内部には、原子炉容器本体22を収容す
る炉容器室24と、原子炉容器22の上部を覆う格納ド
ーム25を収容する炉上部室26が形成されている。炉
上部室26と炉容器室24の境界には段部が形成され、
この段部には原子炉支持プレート27が固定され、原子
炉容器22を支持する原子炉支持部28を構成してい
る。原子炉容器22は上端が原子炉支持プレート27上
に固定され、原子炉支持プレート27を中心に上下方向
に熱伸縮可能に支持されている。炉容器室24の回りの
原子炉格納構造物23のコンクリート壁体の内部には、
炉容器室24に冷却用空気を導入する給気ダクト29が
形成されている。この給気ダクト29のやや上方位置の
原子炉格納構造物23のコンクリート壁体内部には、原
子炉容器22を冷却した高温の空気を排出する排気ダク
ト30が形成されている。給気ダクト29と排気ダクト
30の間の炉容器室24の内壁には内方に突出する突出
部31が形成されている。この突出部31には、原子炉
容器22より大径な炉容器空冷筒32がその上端に形成
されたフランジ部32aで固着されている。この炉容器
空冷筒32は給気ダクト29と排気ダクト30の間に長
い冷却用の空気流路を形成している。この従来の高速増
殖炉21では、原子炉容器22が内部の核燃料の核分裂
に伴って温度が上昇するので、給気ダクト29と冷却用
空気流路と排気ダクト30とに空気を流通させて原子炉
容器22の過度の温度上昇を防止する必要がある。冷却
用の空気は、給気ダクト29から炉容器室24内に導入
され、図4の矢印に示すように、最初に炉容器空冷筒3
2と炉容器室24内壁の間に形成された空気流路に沿っ
て下降し、炉容器室24の内壁を冷却する。次に、冷却
用空気は炉容器空冷筒32下側の開放端から炉容器空冷
筒32と原子炉容器22の間に形成された空気流路に流
入し、原子炉容器22を冷却しつつ上昇する。原子炉容
器22を冷却した高温の空気は炉容器室24の上部空間
24aに達し、自然対流あるいは強制的な送風圧力によ
って排気ダクトを介して外部に排出される。
FIG. 4 shows a configuration of a conventional fast breeder reactor. The conventional fast breeder reactor 21 has a reactor vessel 22, which is housed inside a reactor containment structure 23 constructed of concrete. Inside the reactor containment structure 23, a reactor vessel chamber 24 for accommodating the reactor vessel main body 22 and a reactor upper chamber 26 for containing a containment dome 25 covering the upper part of the reactor vessel 22 are formed. A step is formed at the boundary between the furnace upper chamber 26 and the furnace container chamber 24,
A reactor support plate 27 is fixed to this step, and constitutes a reactor support 28 that supports the reactor vessel 22. The upper end of the reactor vessel 22 is fixed on the reactor support plate 27, and the reactor vessel 22 is supported so as to be thermally expandable and contractible in the vertical direction about the reactor support plate 27. Inside the concrete wall of the containment structure 23 around the reactor chamber 24,
An air supply duct 29 for introducing cooling air into the furnace chamber 24 is formed. An exhaust duct 30 for discharging high-temperature air that has cooled the reactor vessel 22 is formed inside the concrete wall of the reactor containment structure 23 at a position slightly above the air supply duct 29. A projecting portion 31 that projects inward is formed on the inner wall of the furnace chamber 24 between the air supply duct 29 and the exhaust duct 30. A reactor vessel air-cooled cylinder 32 having a diameter larger than that of the reactor vessel 22 is fixed to the protruding portion 31 by a flange portion 32a formed at the upper end thereof. The furnace vessel air cooling cylinder 32 forms a long cooling air flow path between the air supply duct 29 and the exhaust duct 30. In this conventional fast breeder reactor 21, the temperature of the reactor vessel 22 rises with the fission of the nuclear fuel inside, so that the air flows through the air supply duct 29, the cooling air flow path, and the exhaust duct 30 so that the atomic It is necessary to prevent the temperature of the furnace vessel 22 from rising excessively. Cooling air is introduced from the air supply duct 29 into the furnace vessel chamber 24, and as shown by the arrow in FIG.
It descends along the air flow path formed between 2 and the inner wall of the furnace chamber 24, and cools the inner wall of the furnace chamber 24. Next, the cooling air flows into the air flow path formed between the reactor vessel air-cooling cylinder 32 and the reactor vessel 22 from the open end below the reactor vessel air-cooling cylinder 32, and rises while cooling the reactor vessel 22. I do. The high-temperature air that has cooled the reactor vessel 22 reaches the upper space 24a of the reactor vessel chamber 24, and is discharged outside through an exhaust duct by natural convection or forced blast pressure.

【0004】[0004]

【発明が解決しようとする課題】しかしながら、上記従
来の小型高速増殖炉では、冷却用空気が炉容器空冷筒と
原子炉容器の間の空気流路を上昇し、原子炉容器の熱を
吸収して高温となって炉容器室の上部空間に一時的に停
滞するので、炉容器室上部の構造部材(コンクリート)
が高温の空気の影響によって、温度が上昇してしまうこ
とがあった。炉容器室上部のコンクリートは、原子炉容
器を支持する原子炉支持部を構成するので、過度に温度
が上昇した場合には、コンクリートの構造強度が低下
し、原子炉の安全性・信頼性を損なうことがあった。こ
のことは原子炉格納構造物が鋼で構成されている場合に
も、高温による鋼の強度低下によって原子炉の安全性・
信頼性を損なう。これに対して従来の高速増殖炉では、
炉容器室上部の温度上昇を防止するために、炉容器室の
壁面に断熱材を設け、さらに原子炉支持部のコンクリー
トを局部的に冷却するローカルクーラーなどの設備を設
けていた。しかし、これら対応策は効果が十分でなく、
かつ、高速増殖炉の構造を複雑にする問題があった。そ
こで本発明の目的は、上記従来の高速増殖炉の問題を解
決し、原子炉格納構造物の構造部材の過度の温度上昇を
防止するとともに、構造が簡単な高速増殖炉を提供する
ことにある。
However, in the above-mentioned conventional small-sized fast breeder reactor, the cooling air rises in the air flow path between the reactor vessel air-cooled cylinder and the reactor vessel to absorb the heat of the reactor vessel. And becomes temporarily hot and stagnates temporarily in the upper space of the furnace vessel, so structural members (concrete) on the upper part of the furnace vessel
However, the temperature sometimes increased due to the influence of high-temperature air. The concrete in the upper part of the reactor vessel room constitutes the reactor support that supports the reactor vessel, so if the temperature rises excessively, the structural strength of the concrete will decrease and the safety and reliability of the reactor will be reduced. There was a loss. This means that even if the reactor containment structure is made of steel, the safety of the
Impairs reliability. On the other hand, in the conventional fast breeder reactor,
In order to prevent a rise in the temperature of the upper part of the reactor vessel chamber, a heat insulating material was provided on the wall surface of the reactor vessel chamber, and equipment such as a local cooler for locally cooling the concrete of the reactor support was provided. However, these measures are not effective enough,
In addition, there is a problem that the structure of the fast breeder reactor is complicated. Therefore, an object of the present invention is to solve the above-mentioned problems of the conventional fast breeder reactor, to prevent an excessive rise in temperature of the structural members of the reactor containment structure, and to provide a fast breeder reactor having a simple structure. .

【0005】[0005]

【課題を解決するための手段】上記目的を達成するため
に、本発明の高速増殖炉は、原子炉格納構造物内部に形
成された炉容器室に原子炉容器を収容し、原子炉支持リ
ングを介して前記原子炉格納構造物の一部に形成された
原子炉支持部によって前記原子炉容器を支持し、この原
子炉容器の周囲に空気流路を形成する炉容器空冷筒を設
け、前記空気流路に冷却用空気を流通させて原子炉容器
を冷却するようにした高速増殖炉において、前記炉容器
空冷筒はその内側と外側に連続する高温空気流路と低温
空気流路をそれぞれ形成し、前記原子炉支持リングは空
気流入用の貫通孔を備えて低温空気流路の空気流入部に
配設され、前記高温空気流路の空気排出部は前記炉容器
空冷筒と低温空気流路とを貫通して高温空気を外部に排
出する空気排出手段を有していることを特徴とするもの
である。
In order to achieve the above object, a fast breeder reactor according to the present invention comprises a reactor vessel housed in a reactor containment structure and a reactor vessel housed therein. The reactor vessel is supported by a reactor support portion formed in a part of the reactor containment structure through, and a reactor vessel air-cooled cylinder that forms an air flow path around the reactor vessel is provided. In a fast breeder reactor that cools a reactor vessel by flowing cooling air through an air flow path, the reactor vessel air-cooled cylinder forms a continuous high-temperature air flow path and a low-temperature air flow path inside and outside thereof, respectively. The reactor support ring has a through hole for inflow of air, and is disposed at an air inflow portion of the low temperature air flow passage. The air discharge portion of the high temperature air flow passage is provided with the reactor vessel air cooling cylinder and the low temperature air flow passage. Air discharger that discharges high-temperature air to the outside through To have is characterized in.

【0006】[0006]

【作用】本発明による高速増殖炉は、原子炉容器より大
径の炉容器空冷筒によって炉容器室内部空間を仕切り、
原子炉容器に接する外周部に高温空気流路を形成し、炉
容器空冷筒の外側に炉容器室に接する低温空気流路を形
成し、この低温空気流路と高温空気流路とを互いに連続
させ、さらに空気流入用の貫通孔を備えた原子炉支持リ
ングを低温空気流路の空気流入部に配設し、高温空気流
路の空気排出部に炉容器空冷筒と低温空気流路を貫通し
て外部に高温の空気を排出する空気排出手段を設けてい
る。上記構成により本発明の高速増殖炉では、冷却用空
気は最初に原子炉支持リング及び原子炉支持部を通って
低温空気流路を流通し、次に高温空気流路を流通して最
終的に空気排出手段を通って外部空間に排出される。低
温空気流路の空気流入部では冷却用空気が未だ熱せられ
ていないので、原子炉支持部および原子炉支持リングを
低い温度に維持することができる。また、低温空気流路
は高温空気流路を内包するように形成されているので、
炉容器室の内壁は高温の空気に直接触れることない。ま
た、高温空気流路では、空気は原子炉容器に比べて低い
温度を有しているので、十分な冷却効果を有し、かつ、
高温空気流路末端の空気排出部で高温となった空気は空
気排出手段によって直接外部に排出され、低温空気流路
や原子炉支持部に熱影響を与えることない。以上の各作
用により、本発明の高速増殖炉では、原子炉容器の熱が
原子炉格納構造物の構造部材に強度上の影響を与えるこ
となく外部空間に直接放出されるので、原子炉格納構造
物の構造部材の強度が維持され、原子炉の安全性・信頼
性の向上を図ることができる。
In the fast breeder reactor according to the present invention, the space inside the reactor vessel chamber is partitioned by a reactor vessel air-cooled cylinder having a diameter larger than that of the reactor vessel.
A high-temperature air flow path is formed on the outer peripheral part in contact with the reactor vessel, and a low-temperature air flow path is formed on the outside of the reactor vessel air-cooling cylinder. The low-temperature air flow path and the high-temperature air flow path are connected to each other. In addition, a reactor support ring provided with a through hole for air inflow is arranged in the air inflow section of the low temperature air flow path, and the furnace vessel air cooling cylinder and the low temperature air flow path pass through the air discharge section of the high temperature air flow path. And an air discharging means for discharging high-temperature air to the outside. With the above configuration, in the fast breeder reactor of the present invention, the cooling air first flows through the low-temperature air flow path through the reactor support ring and the reactor support, then flows through the high-temperature air flow path, and finally flows. The air is discharged to the external space through the air discharging means. Since the cooling air has not yet been heated in the air inlet of the low-temperature air flow passage, the temperature of the reactor support and the reactor support ring can be maintained at a low temperature. Also, since the low-temperature air flow path is formed to include the high-temperature air flow path,
The inner wall of the furnace chamber does not come into direct contact with hot air. Also, in the high-temperature air flow path, the air has a lower temperature than the reactor vessel, so that it has a sufficient cooling effect, and
The air that has become hot at the air discharge section at the end of the high-temperature air flow path is directly discharged to the outside by the air discharge means and does not affect the low-temperature air flow path or the reactor support section. By the above-described operations, in the fast breeder reactor of the present invention, the heat of the reactor vessel is directly released to the external space without affecting the strength of the structural members of the reactor containment structure. The strength of the structural member of the product is maintained, and the safety and reliability of the reactor can be improved.

【0007】[0007]

【実施例】本発明は炉容器空冷筒によってその内側と外
側に連続する高温空気流路と低温空気流路をそれぞれ形
成し、低温空気流路の空気流入部に低温環境が求められ
る原子炉支持部を配置し、空気が最も高温となる高温空
気流路の空気排出部に原子炉格納構造物に熱を伝達する
ことなく、高温空気を直接外部に排出する空気排出手段
を設けものである。以下本発明の実施例について添付の
図面を参照して説明する。図1は本発明の第1実施例に
よる高速増殖炉の構成を示している。全体を符号1で示
す高速増殖炉は、炉心を収容する原子炉容器2を有して
いる。原子炉格納構造物3は全体がコンクリートによっ
て形成され、内部に原子炉容器2の本体を収容する炉容
器室4と、原子炉容器2の上部を覆う格納ドーム5を収
容する炉上部室6が形成されている。炉上部室6と炉容
器室4の境界には段部が形成され、この段部は原子炉容
器2を支持する原子炉支持部7を構成している。原子炉
容器2は原子炉支持部7上に固定された原子炉支持リン
グ8上に固定され、原子炉支持リング8を中心に上下に
熱伸縮可能に支持されている。原子炉格納構造物3のコ
ンクリート壁体内部には、炉上部室6の上部に連通する
給気ダクト9と、炉容器室4の上部に連通する排気ダク
ト10とが形成されている。原子炉容器2の周囲には間
隔を隔てて原子炉容器2の外周壁を取り囲む炉容器空冷
筒11が配設されている。この炉容器空冷筒11は上端
が原子炉容器2の上部に接続され、下端は炉容器室4の
下部空間に開放されている。炉容器空冷筒11の上部に
は、図2に明らかに示すように、一端が排気ダクトに接
続され、他端が炉容器空冷筒11の内側の空間に連通す
る排気ベローズ12が設けられている。また、原子炉支
持リング8は図2に示すように、所定の高さの円筒部8
aを有し、この円筒部8aには複数の空気を流通させる
貫通孔13が穿設されている。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention relates to a reactor support in which a high-temperature air flow path and a low-temperature air flow path are respectively formed inside and outside by a furnace vessel air-cooled cylinder, and a low-temperature environment is required at the air inlet of the low-temperature air flow path. And an air discharge means for directly discharging the high-temperature air to the outside without transmitting heat to the reactor containment structure at the air discharge portion of the high-temperature air flow path where the air has the highest temperature. Hereinafter, embodiments of the present invention will be described with reference to the accompanying drawings. FIG. 1 shows a configuration of a fast breeder reactor according to a first embodiment of the present invention. The fast breeder reactor generally denoted by reference numeral 1 has a reactor vessel 2 that houses a reactor core. The reactor containment structure 3 is entirely made of concrete, and includes a reactor vessel chamber 4 for housing the main body of the reactor vessel 2 therein and a furnace upper chamber 6 for containing a containment dome 5 for covering the upper part of the reactor vessel 2. Is formed. A step is formed at the boundary between the furnace upper chamber 6 and the reactor vessel chamber 4, and this step constitutes a reactor support 7 for supporting the reactor vessel 2. The reactor vessel 2 is fixed on a reactor support ring 8 fixed on a reactor support section 7 and is supported so as to be vertically expandable and contractible about the reactor support ring 8. An air supply duct 9 communicating with an upper part of the furnace upper chamber 6 and an exhaust duct 10 communicating with an upper part of the reactor vessel chamber 4 are formed inside the concrete wall of the reactor containment structure 3. A reactor vessel air-cooled cylinder 11 surrounding the outer peripheral wall of the reactor vessel 2 is provided around the reactor vessel 2 at an interval. The furnace vessel air-cooled cylinder 11 has an upper end connected to the upper part of the reactor vessel 2 and a lower end opened to a lower space of the furnace vessel chamber 4. As clearly shown in FIG. 2, an exhaust bellows 12 having one end connected to the exhaust duct and the other end communicating with the space inside the furnace container air cooling cylinder 11 is provided at the upper part of the furnace container air cooling cylinder 11. . As shown in FIG. 2, the reactor support ring 8 has a cylindrical portion 8 having a predetermined height.
The cylindrical portion 8a has a through hole 13 through which a plurality of air flows.

【0008】上記構造に基づいて本実施例の作用につい
て以下に説明する。本実施例の高速増殖炉1は、原子炉
容器2によって核燃料の集合体からなる炉心(図示せ
ず)を収容し、この炉心を核分裂させて熱を発生させ、
この熱を液体ナトリウム等の1次冷却材と水等の2次冷
却材とによって外部に取り出し、動力に変換する。した
がって、運転中は原子炉容器2が高温になり、これを冷
却し続ける必要がある。図1および図2の矢印は冷却用
の空気の流れを示している。図1に示すように、冷却用
空気は給気ダクト9からフィルター14を経て炉上部室
6に流入し、次に原子炉支持リング8の貫通孔13を通
って炉容器室4に流入し、次に炉容器空冷筒11と原子
炉容器2の間の空気流路を上昇して排気ベローズ12と
排気ダクト10とを通って外部空間に排出される。この
空気の流動は強制的な送風と自然通風の双方によって行
うことができるように構成されている。この場合、炉容
器空冷筒11の外側と炉容器室4の内壁の間の空間は低
温空気流路Lを構成し、炉容器空冷筒11の内側と原子
炉容器2の外側の間の空間は高温空気流路Hを構成す
る。冷却用空気は炉上部室6を流通した後に、原子炉支
持リング8と原子炉支持部7を冷却しつつ炉容器室4の
低温空気流路Lに流入する。低温空気流路Lでは、空気
は炉容器室4の壁面と高温空気流路Hの間の熱の伝達を
遮断して流動する。次に、空気は炉容器空冷筒11の下
端から高温空気流路Hに流入し、原子炉容器2を冷却し
つつ高温空気流路H内を上昇する。高温空気流路Hの上
端の空気排出部Haに達した高温の空気は原子炉支持リ
ング8や原子炉支持部7に熱影響を与えることなく、排
気ベローズ12を介して排気ダクト10に排出される。
上述した冷却空気の流動経路により、原子炉支持部7と
原子炉支持リング8は低温空気流路Lの空気流入部La
に位置して常時低温の空気によって冷却され、さらに冷
却を完了した高温の空気は原子炉支持部7と原子炉支持
リング8を熱することなく排出されるので、原子炉支持
部7は確実に低温に維持され、これによって原子炉の安
全性と信頼性の向上を図ることができる。また、原子炉
支持部7を局部的に冷却するローカルクーラー等の特別
な設備や断熱材を設ける必要がないので、構造が簡単な
高速増殖炉1を得ることができる。
The operation of this embodiment will be described below based on the above structure. In the fast breeder reactor 1 of the present embodiment, a reactor core (not shown) composed of an assembly of nuclear fuel is accommodated in a reactor vessel 2, and the core is fissioned to generate heat,
This heat is taken out to the outside by a primary coolant such as liquid sodium and a secondary coolant such as water, and converted into power. Therefore, during operation, the temperature of the reactor vessel 2 becomes high, and it is necessary to keep it cooled. The arrows in FIGS. 1 and 2 indicate the flow of cooling air. As shown in FIG. 1, the cooling air flows from the air supply duct 9 through the filter 14 into the furnace upper chamber 6, then flows into the reactor vessel chamber 4 through the through hole 13 of the reactor support ring 8, Next, the air is flown up between the furnace vessel air-cooled cylinder 11 and the reactor vessel 2 and is discharged to the external space through the exhaust bellows 12 and the exhaust duct 10. The flow of the air is configured to be able to be performed by both forced ventilation and natural ventilation. In this case, the space between the outside of the furnace vessel air cooling cylinder 11 and the inner wall of the furnace vessel chamber 4 forms a low-temperature air flow path L, and the space between the inside of the furnace vessel air cooling cylinder 11 and the outside of the reactor vessel 2 is The high-temperature air flow path H is configured. After flowing through the furnace upper chamber 6, the cooling air flows into the low-temperature air flow path L of the reactor vessel chamber 4 while cooling the reactor support ring 8 and the reactor support 7. In the low-temperature air flow path L, air flows by interrupting the transfer of heat between the wall surface of the furnace chamber 4 and the high-temperature air flow path H. Next, the air flows into the high-temperature air flow path H from the lower end of the reactor vessel air-cooled cylinder 11 and rises in the high-temperature air flow path H while cooling the reactor vessel 2. The high-temperature air that has reached the air discharge portion Ha at the upper end of the high-temperature air flow path H is discharged to the exhaust duct 10 via the exhaust bellows 12 without affecting the reactor support ring 8 and the reactor support portion 7 thermally. You.
Due to the flow path of the cooling air described above, the reactor support 7 and the reactor support ring 8 are connected to the air inlet La of the low-temperature air flow path L.
Is cooled by low-temperature air at all times, and the high-temperature air that has been further cooled is discharged without heating the reactor support 7 and the reactor support ring 8. It is maintained at a low temperature, which can improve the safety and reliability of the reactor. In addition, since it is not necessary to provide any special equipment such as a local cooler for locally cooling the reactor support portion 7 or a heat insulating material, the fast breeder reactor 1 having a simple structure can be obtained.

【0009】なお、本発明は炉容器空冷筒の内側と外側
に高温空気流路と低温空気流路とを形成し、低温空気流
路の空気流入部に原子炉支持部を配置し、高温空気流路
の末端に高温の空気を排出する空気排出手段を設けてい
れば良く、給気ダクトと排気ダクトの位置や、空気排出
手段の具体的構成に限定されない。以下に原子炉支持リ
ングの貫通孔に給気ダクトを接続した本発明の第2実施
例について説明する。図3は原子炉支持リングの貫通孔
に給気ダクトを直接接続した本発明の第2実施例の構成
を示している。図1と同一部分に同一符号を付して説明
を省略した図3において、原子炉支持リング15は炉容
器室4の上端部の原子炉格納構造物3のコンクリート中
に埋設され、円筒部15aの所定箇所には空気流入用の
貫通孔16が設けられている。また、原子炉格納構造物
3のコンクリートの壁体中には出口が貫通孔16と整合
する給気ダクト17が形成されている。この実施例によ
れば、冷却用空気は熱せられることなく最初に原子炉支
持リング15を冷却するので、原子炉支持リング15の
金属による放熱性の良さから原子炉支持部7を効果的に
低温に維持することができる。
According to the present invention, a high-temperature air flow path and a low-temperature air flow path are formed inside and outside a reactor vessel air-cooled cylinder, and a reactor support is disposed at an air inlet of the low-temperature air flow path. Air discharge means for discharging high-temperature air may be provided at the end of the flow path, and is not limited to the positions of the air supply duct and the exhaust duct and the specific configuration of the air discharge means. Hereinafter, a second embodiment of the present invention in which an air supply duct is connected to a through hole of a reactor support ring will be described. FIG. 3 shows a configuration of a second embodiment of the present invention in which an air supply duct is directly connected to a through hole of a reactor support ring. In FIG. 3, in which the same reference numerals are given to the same parts as in FIG. 1 and the description is omitted, the reactor support ring 15 is buried in the concrete of the reactor containment structure 3 at the upper end of the reactor chamber 4, and the cylindrical part 15a Is provided with a through hole 16 for inflow of air at a predetermined location. Further, an air supply duct 17 whose outlet is aligned with the through hole 16 is formed in the concrete wall of the reactor containment structure 3. According to this embodiment, since the cooling air first cools the reactor support ring 15 without being heated, the reactor support portion 7 can be effectively cooled at a low temperature due to the good heat radiation of the reactor support ring 15 by the metal. Can be maintained.

【0010】[0010]

【発明の効果】上記の説明から明らかなように、本発明
による高速増殖炉は、原子炉容器より大径の炉容器空冷
筒によって原子炉容器の周囲に高温空気流路を形成し、
この高温空気流路の外側に低温空気流路を形成し、低温
空気流路の空気流入部に原子炉支持部と原子炉支持リン
グを配置し、高温空気流路の空気排出部に高温の空気を
直接外部に排出する空気排出手段を設けているので、運
転中に原子炉支持部と原子炉支持リングが低温の空気に
よって連続的に冷却され、確実に低温に維持される。こ
れにより、原子炉支持リングや原子炉支持部の構造上の
強度が高温によって低下することなく、原子炉全体の安
全性・信頼性の向上を図ることができる。また、本発明
の高速増殖炉は原子炉支持部等が低温の空気によって冷
却され続けるので、ローカルクーラー等の特別な設備を
設ける必要がなく、構造が簡単な高速増殖炉を得ること
ができる。
As is apparent from the above description, the fast breeder reactor according to the present invention forms a high-temperature air flow path around the reactor vessel by a reactor vessel air-cooled cylinder having a diameter larger than that of the reactor vessel.
A low-temperature air flow path is formed outside the high-temperature air flow path, a reactor support section and a reactor support ring are arranged at an air inlet of the low-temperature air flow path, and high-temperature air is supplied to an air discharge section of the high-temperature air flow path. Is provided, the reactor support and the reactor support ring are continuously cooled by low-temperature air during operation, and are reliably maintained at a low temperature. As a result, the safety and reliability of the entire reactor can be improved without the structural strength of the reactor support ring and the reactor support being reduced by the high temperature. Further, in the fast breeder reactor of the present invention, since the reactor support portion and the like are continuously cooled by low-temperature air, there is no need to provide special equipment such as a local cooler, and a fast breeder reactor having a simple structure can be obtained.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明の第1実施例による高速増殖炉の構成を
示した図。
FIG. 1 is a diagram showing a configuration of a fast breeder reactor according to a first embodiment of the present invention.

【図2】本発明の第1実施例の原子炉支持部を拡大して
示した断面図。
FIG. 2 is an enlarged cross-sectional view of a reactor support according to the first embodiment of the present invention.

【図3】本発明の第2実施例による高速増殖炉の構成を
示した図。
FIG. 3 is a diagram showing a configuration of a fast breeder reactor according to a second embodiment of the present invention.

【図4】従来の高速増殖炉の構成を示した図。FIG. 4 is a diagram showing a configuration of a conventional fast breeder reactor.

【符号の説明】[Explanation of symbols]

1 高速増殖炉 2 原子炉容器 3 原子炉格納構造物 4 炉容器室 7 原子炉支持部 8 原子炉支持リング 11 炉容器空冷筒 12 排気ベローズ 13 貫通孔 L 低温空気流路 La 低温空気流路の空気流入部 H 高温空気流路 Ha 高温空気流路の空気排出部 DESCRIPTION OF SYMBOLS 1 Fast breeder reactor 2 Reactor vessel 3 Reactor containment structure 4 Reactor vessel room 7 Reactor support part 8 Reactor support ring 11 Reactor vessel air-cooled cylinder 12 Exhaust bellows 13 Through hole L Low temperature air flow path La Low temperature air flow path Air inlet H High temperature air channel Ha Air outlet of high temperature air channel

───────────────────────────────────────────────────── フロントページの続き (72)発明者 中 村 博 神奈川県横浜市鶴見区末広町2丁目4番 地 株式会社東芝 京浜事業所内 (72)発明者 服 部 禎 男 東京都千代田区大手町一丁目6番1号 財団法人電力中央研究所内 (56)参考文献 特開 昭63−58291(JP,A) 特開 平3−18792(JP,A) 特開 平3−18793(JP,A) 特開 平4−232496(JP,A) 特開 平5−196778(JP,A) 特開 平5−196779(JP,A) 特開 平5−196780(JP,A) (58)調査した分野(Int.Cl.7,DB名) G21C 15/12 G21C 1/02 G21C 13/02 ──────────────────────────────────────────────────続 き Continued on the front page (72) Hiroshi Nakamura 2-4, Suehirocho, Tsurumi-ku, Yokohama-shi, Kanagawa Prefecture Inside Keihin Plant, Toshiba Corporation (72) Inventor Sadao Hattori Otemachi, Chiyoda-ku, Tokyo No. 6-1 in the Central Research Institute of Electric Power Industry (56) References JP-A-63-58291 (JP, A) JP-A-3-18792 (JP, A) JP-A-3-18793 (JP, A) JP-A-4-232496 (JP, A) JP-A-5-196778 (JP, A) JP-A-5-196779 (JP, A) JP-A-5-196780 (JP, A) (58) Int.Cl. 7 , DB name) G21C 15/12 G21C 1/02 G21C 13/02

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】原子炉格納構造物内部に形成された炉容器
室に原子炉容器を収容し、原子炉支持リングを介して前
記原子炉格納構造物の一部に形成された原子炉支持部に
よって前記原子炉容器を支持し、この原子炉容器の周囲
に空気流路を形成する炉容器空冷筒を設け、前記空気流
路に冷却用空気を流通させて原子炉容器を冷却するよう
にした高速増殖炉において、 前記炉容器空冷筒はその内側と外側に連続する高温空気
流路と低温空気流路をそれぞれ形成し、前記原子炉支持
リングは空気流入用の貫通孔を備えて低温空気流路の空
気流入部に配設され、前記高温空気流路の空気排出部は
前記炉容器空冷筒と低温空気流路とを貫通して高温空気
を外部に排出する空気排出手段を有していることを特徴
とする高速増殖炉。
A reactor vessel is housed in a reactor vessel chamber formed inside a reactor containment structure, and a reactor support portion formed on a part of the reactor containment structure via a reactor support ring. The reactor vessel is supported by the reactor vessel, and a reactor vessel air-cooled cylinder forming an air flow path is provided around the reactor vessel, and cooling air is circulated through the air flow path to cool the reactor vessel. In the fast breeder reactor, the reactor vessel air-cooled cylinder forms a continuous high-temperature air flow path and a low-temperature air flow path inside and outside thereof, and the reactor support ring has a through hole for air inflow, and the low-temperature air flow is provided. The high-temperature air flow passage has an air discharge unit that is disposed at an air inflow portion and that discharges high-temperature air to the outside through the furnace vessel air-cooling cylinder and the low-temperature air flow passage. A fast breeder reactor characterized in that:
JP04324471A 1992-07-30 1992-12-03 Fast breeder reactor Expired - Lifetime JP3110901B2 (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
JP04324471A JP3110901B2 (en) 1992-12-03 1992-12-03 Fast breeder reactor
US08/097,833 US5420897A (en) 1992-07-30 1993-07-29 Fast reactor having reflector control system
FR9309410A FR2697104B1 (en) 1992-07-30 1993-07-30 Fast reactor equipped with a control system for reflector.

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP04324471A JP3110901B2 (en) 1992-12-03 1992-12-03 Fast breeder reactor

Publications (2)

Publication Number Publication Date
JPH06174884A JPH06174884A (en) 1994-06-24
JP3110901B2 true JP3110901B2 (en) 2000-11-20

Family

ID=18166180

Family Applications (1)

Application Number Title Priority Date Filing Date
JP04324471A Expired - Lifetime JP3110901B2 (en) 1992-07-30 1992-12-03 Fast breeder reactor

Country Status (1)

Country Link
JP (1) JP3110901B2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR102192650B1 (en) * 2019-03-18 2020-12-17 한국전력기술 주식회사 Cooling water storage tank passive cooling device for containment passive cooling system

Also Published As

Publication number Publication date
JPH06174884A (en) 1994-06-24

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