JPS59195198A - Heat exchanger installed in natural circulation type reactor - Google Patents
Heat exchanger installed in natural circulation type reactorInfo
- Publication number
- JPS59195198A JPS59195198A JP58070557A JP7055783A JPS59195198A JP S59195198 A JPS59195198 A JP S59195198A JP 58070557 A JP58070557 A JP 58070557A JP 7055783 A JP7055783 A JP 7055783A JP S59195198 A JPS59195198 A JP S59195198A
- Authority
- JP
- Japan
- Prior art keywords
- heat exchanger
- reactor
- pressure vessel
- natural circulation
- core
- 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.)
- Granted
Links
Classifications
-
- 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
-
- 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
Landscapes
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、地域冷暖房、化学コンビナート等への熱供給
を目的とした自然循環型原子炉内に設置する熱交換器に
関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a heat exchanger installed in a natural circulation nuclear reactor for the purpose of supplying heat to district heating and cooling systems, chemical complexes, and the like.
一般に自然循環型軽水炉における熱供給炉システムは原
子炉で発生した熱を、温水又は蒸気の形態で需要先に供
給するものである。このような熱供給原子炉システムの
設計例を第１図に示す。原子炉サイト２３で発生した熱
はサブステーション２３を経由して需要先に輸送される
。先ず、炉心２６で発生した熱は、−火熱交換器２７に
より二次ループ２８に伝達される。−火熱交換器の配置
に関しては、圧力容器内蔵型と圧力容器外置型に大別さ
れる。ここでは内蔵型の例を示した。二次ループの熱は
更に、二次熱交換器３１を経由して三次ループ３２に伝
達され、サブステーション２内の端末熱交換器３５を経
由して各個別需要先に輸送される。Generally, a heat supply reactor system in a natural circulation light water reactor supplies heat generated in a nuclear reactor to a consumer in the form of hot water or steam. A design example of such a heat supply reactor system is shown in FIG. Heat generated at the reactor site 23 is transported to the demand destination via the substation 23. First, heat generated in the core 26 is transferred to the secondary loop 28 by the -fire heat exchanger 27 . - Regarding the arrangement of fire heat exchangers, there are two types: built-in pressure vessel type and external pressure vessel type. Here we show an example of a built-in type. The heat in the secondary loop is further transferred to the tertiary loop 32 via the secondary heat exchanger 31, and is transported to each individual consumer via the terminal heat exchanger 35 in the substation 2.
このようなシステムにおける一次熱交換器の配置は、シ
ステム全体のコンパクト化の観点から、内蔵型が望まし
いが、従来の設計例では次のような離点を有している。As for the arrangement of the primary heat exchanger in such a system, from the viewpoint of making the entire system more compact, it is desirable to use a built-in type, but conventional design examples have the following separation points.
第１に、圧力容器内に大型構造を持ち込む畑点。First, Hata-tome brings a large structure into the pressure vessel.
従来、伝熱管をスパイラル型とし、圧力容器内外周部の
猿状下降部に一体配置する設計例があるが、仮に圧力容
器からの取出し方法が考案されたとしても、大型構造で
あるため取出しおよび再設置に難点がある。Conventionally, there is an example of a design in which the heat transfer tube is spiral-shaped and is integrally arranged in the monkey-like descending part of the inner and outer periphery of the pressure vessel, but even if a method for taking it out from the pressure vessel was devised, it would be difficult to take it out and take it out because of its large structure. There are difficulties in reinstallation.
第２に、熱交換器の圧力容器からの取シはすしに係る難
点。従来、冷却材導出入管が圧力容器主７ランジ下部を
貫通ずる設計例があるが、貫通部を極少化したものは溶
接構造とな）、熱交換器は圧力容器に固定されることに
なり１熊交換器の圧力容器からの取り出しが不可となる
。Second, removing the heat exchanger from the pressure vessel is a problem with sushi. Conventionally, there is an example of a design in which the coolant inlet/output pipe passes through the lower part of the main 7 flange of the pressure vessel, but the one that minimizes the penetration part is a welded structure), and the heat exchanger is fixed to the pressure vessel. The bear exchanger cannot be removed from the pressure vessel.
第３に、分割熱交換器の形態が適格でないと、圧力容器
断面部が大型になシ圧力容器内に不用壁間が発生する。Thirdly, if the form of the split heat exchanger is not suitable, the cross section of the pressure vessel will be large and unnecessary gaps will occur in the pressure vessel.
発明者等はこれら問題点を解決するため下記の課題に対
応する必要があることを理解した。The inventors have understood that in order to solve these problems, it is necessary to address the following issues.
第１に、熱交換器は点検、保修に最適なサイズに分割さ
れ、かつ冷却材導出入管は、−次系冷却材の自然循環を
阻害しない配管構造とする。First, the heat exchanger is divided into sizes optimal for inspection and maintenance, and the coolant inlet and outlet pipes have a piping structure that does not inhibit the natural circulation of the secondary coolant.
第２に、熱交換器取出し作業と燃料交換作業が相互独立
に実行できる構造とする。Second, the structure is such that the heat exchanger removal work and the fuel exchange work can be performed independently of each other.
第３に、分割熱交の圧力容器からの取り出し方式と冷却
材導出入管と圧力容器の分離接続機構を設けること。Thirdly, a method for extracting the divided heat exchanger from the pressure vessel and a separate connection mechanism between the coolant inlet/output pipe and the pressure vessel are provided.
本発明の目的は、上述する課題を解決し、原子炉−次系
自然循現システムに適合し、点検、保守の容易な構造の
自然循環型原子炉内に設置する熱交換器を提供すること
にある。An object of the present invention is to solve the above-mentioned problems and provide a heat exchanger installed in a natural circulation reactor that is compatible with the reactor-subsystem natural circulation system and has a structure that is easy to inspect and maintain. It is in.
本発明の実施例を第２図に示した。炉心は燃料集合体１
１とそれを支持する下部炉心支持板１および上部炉心支
持板１０から４１４成される。制御棒３は、上部よシ制
御棒駆動機構８によシ駆動される。炉心上部には、制御
棒案内管５で構成されるチムニ−があり一次系冷却材の
自然循環の主要駆動力を発生する。炉心で発生した二相
流はチムニ−を上昇しチムニ−上部の自由ｖ面で気液分
離される。分離された液相部分は、圧力容器と炉心シュ
ラウド４および上部シュラウド６で構成される環状流路
を下降し、炉心に戻シ自然循壌流路を一巡する。−火熱
交換器は、この環状流路部において、自由液面１２を貫
通して配置される。熱交換器の下端は炉心からの中性子
による放射化を避けるために炉心よシ必要な距離大保持
することが要請される。熱交換器の上端は一部蒸気相部
に露出する。炉心で発生した蒸気は熱交換器の蒸気相部
に露出した部分で凝縮される。このため気相部の圧力は
一定に保たれるー。この熱交換器の気相部露出部分を凝
縮部と呼称する。熱交換器の液相部分は一次系冷却材の
炉心サブクールを決定するので亜冷却部と呼称される。An embodiment of the invention is shown in FIG. The core is fuel assembly 1
1 and a lower core support plate 1 and an upper core support plate 10 that support it. The control rod 3 is driven by an upper control rod drive mechanism 8. At the upper part of the reactor core, there is a chimney composed of control rod guide tubes 5, which generates the main driving force for the natural circulation of the primary coolant. The two-phase flow generated in the core ascends the chimney and is separated into gas and liquid on the free V surface at the top of the chimney. The separated liquid phase portion descends through the annular flow path composed of the pressure vessel, the core shroud 4, and the upper shroud 6, returns to the core, and goes around the natural circulation flow path. - the fire heat exchanger is arranged in this annular channel section through the free liquid level 12; The lower end of the heat exchanger is required to be kept at a necessary distance from the core to avoid activation by neutrons from the core. The upper end of the heat exchanger is partially exposed to the vapor phase. Steam generated in the core is condensed in the heat exchanger exposed to the steam phase. Therefore, the pressure in the gas phase remains constant. The exposed part of the gas phase of the heat exchanger is called the condensing part. The liquid phase part of the heat exchanger is called the subcooling part because it determines the core subcooling of the primary coolant.
二次ループの冷却材は、圧力容器上部の鏡板の貫通部を
経由し、熱交換部に流入する。図中左側に熱交換器下降
部、右側に熱交換器上昇部を示しである。二次冷却材は
下降管１３を下降し、下部ヘッダー１４で各伝熱管１５
に分配される。伝熱管の亜冷却部、凝縮部で加熱された
冷却材は、上部ヘッダー１６に集められ、上昇管１７を
通り、貫通部１８から圧力容器外部に流出する。The coolant in the secondary loop flows into the heat exchange section via the penetration part of the end plate at the top of the pressure vessel. In the figure, the lower part of the heat exchanger is shown on the left side, and the upper part of the heat exchanger is shown on the right side. The secondary coolant descends down the downcomer pipe 13 and passes through each heat transfer tube 15 at the lower header 14.
distributed to. The coolant heated in the subcooling section and the condensing section of the heat transfer tube is collected in the upper header 16, passes through the riser pipe 17, and flows out of the pressure vessel from the penetration section 18.
熱交換器の断面図を第３図に示す。右半分は第２図に示
したＡＡ’断面、左半分はＢＢ’断面である。炉心部右
上半分に燃料果合体、右下半分にチムニ−を示す。外周
部左半分に熱交換器の断〔Ｉｌｌを示す。描図は、円周
方向４分割型の場合を示したものである。分割数は、原
子炉出力、原子炉構成に依存するので、分割数の最適化
については後述する。この様に分割された熱交換器の形
状は凹型短冊状になる。下降管１３は、隣接する分割伝
熱管束１５の間の空隙部を下降し、Ｌ字型に下部へラグ
−に接続する。上部ヘンダーにはほぼその中央部に上昇
管１７が、逆Ｔ字型に接続され、垂直に上部鏡板貫通部
に到る。A cross-sectional view of the heat exchanger is shown in FIG. The right half is the AA' cross section shown in FIG. 2, and the left half is the BB' cross section. The fuel assembly is shown in the upper right half of the reactor core, and the chimney is shown in the lower right half. The heat exchanger cutout [Ill] is shown on the left half of the outer periphery. The drawing shows the case of a four-division type in the circumferential direction. Since the number of divisions depends on the reactor output and reactor configuration, optimization of the number of divisions will be described later. The heat exchanger divided in this way has a concave rectangular shape. The downcomer pipe 13 descends through the gap between the adjacent divided heat exchanger tube bundles 15 and connects to the lower part with a lug in an L shape. A rising pipe 17 is connected to the upper hender almost at its center in an inverted T-shape, and vertically reaches the upper end plate penetration part.
第４図は、猿状下降部にある４分割熱交換器の全断面図
を示したものである。FIG. 4 shows a full sectional view of the four-part heat exchanger in the monkey-shaped descending section.
伝熱管の型式としては直管型、Ｕ字管型、ヘリカルコイ
ル型、ザーペンタイン型等が考えられるが、轟実施例に
おいては、自然循環システムへの適合性、すなわち低圧
力損失、および円周方向への分割可能の観点から直管型
が望ましい。第５図は管束部の断面を示したものである
。伝熱管束は、自由液界面下部Ｂの下部ｇ束２１および
界面上部Ａの上部・−・束２０から薄酸される。冷却材
は下部ヘッダー１４で分配され、上部ヘッダーに集中さ
れる。図中の伝熱管は最外周部と中央部の代表例を示し
たものであるが実機においてはシステムに適合した伝熱
管ピンチ、配列を有する綿密な伝熱管束を構成する。Possible types of heat transfer tubes include straight tube type, U-shaped tube type, helical coil type, and serpentine type, but in Todoroki's example, compatibility with natural circulation systems, that is, low pressure loss, and A straight pipe type is preferable from the viewpoint of being divisible. FIG. 5 shows a cross section of the tube bundle. The heat exchanger tube bundle is lightly acidified from the lower g bundle 21 of the lower free-liquid interface B and the upper bundle 20 of the upper interface A. Coolant is distributed in the lower header 14 and concentrated in the upper header. The heat exchanger tubes in the figure are representative examples of the outermost portion and the center portion, but in the actual machine, they constitute a detailed heat exchanger tube bundle with heat exchanger tube pinches and arrangement suitable for the system.
冷却材導出入管の上部続版貫通部は極力少断面であるこ
とが鏡板の強度設計上望ましく、青白の流速の許容限度
まで管径を紋るものとする。図中、下降管１３は絞り管
適用の例を示したものである。It is desirable for the upper continuous plate penetration part of the coolant inlet/outlet pipe to have as small a cross section as possible in terms of strength design of the end plate, and the pipe diameter shall be increased to the allowable limit of the blue-white flow velocity. In the figure, the downcomer pipe 13 shows an example in which a throttle pipe is applied.
不発明では、管束の円周方向分割の例として４分割案を
示しているが、炉外システムとの相互関係において、適
合する他種の複数分割が可能である。In the present invention, a four-division scheme is shown as an example of circumferential division of the tube bundle, but other types of multiple divisions are possible depending on the relationship with the outside-of-core system.
本発明によれば、圧力容器内への熱交換器のコンパクト
な配置が可能であシ、圧力容器の小型化が達成され、さ
らに、燃料置換お゛よび熱交換器点検、保守作業の効率
向上、定検期間短縮の効果がある。According to the present invention, the heat exchanger can be placed compactly in the pressure vessel, the pressure vessel can be downsized, and the efficiency of fuel replacement, heat exchanger inspection, and maintenance work is improved. , has the effect of shortening periodic inspection period.
第１図は本発明の適用プラントシステム図、第２図、第
３図は本発明の実施例を示す全体断面図、第４図、第５
図は本発明の実施例を示す部分１１ＪＦ而図である。
４・・・炉心シュラウド、６・・・上部シュラウド、７
・・・−火熱交換器、１１・・・燃料集合体、１２・・
・水面、１３・・・下降管、１４・・・下部ヘッダー、
１５・・・伝熱管、１６・・・上部へラダー、１７・・
・上昇管、１８・・・茅 汗
軌３ 図
円
策 ４（２１
馬 ５ （２）
↓１
第１゛頁の続き
０発 明 者 園田猛 ０出福岡
市中央区渡辺通２丁目１香
８２号九州電力株式会社内 ■出
＠発 明 者 高橋義信
東京都千代田区大手町−丁目６＠出
番１号日本原子力発電株式会社
内 ＠出＠発 明 者
桜間直樹
東京都千代田区神田駿河台四丁■出
目６番地株式会社日立製作所内
０発 明 者 堤潔 ■出東京
都千代田区神田駿河台四丁
目６番地株式会社日立製作所内■出
＠発 明 者 秋田実
東京都千代田区神田駿河台四１
目６番地株式会社日立製作所内■出
■出 願 人 東京電力株式会社
東京都千代田区内幸町１丁目１
番３号
■出 願 人 北海道電力株式会社
札幌市中央区大通東１−２
願 人 東北電力株式会社
仙台市１番町３丁目７番１号
願 人 中部電力株式会社
名古屋市東区東新町一番地
願 人 北陸電力株式会社
富山市桜橋通り３番１号
願 人 関西電力株式会社
大阪市中之島三丁目３番２２号
願 人 中国電力株式会社
広島市中区小町４番３３号
願 人 四国電力株式会社
高松型光の内２の５
願 人 九州電力株式会社
福岡市中央区渡辺通２丁目１番
８２号
願 人 日本原子力発電株式会社
東京都千代田区大手町−丁目６
番１号Fig. 1 is a diagram of a plant system to which the present invention is applied; Figs. 2 and 3 are overall cross-sectional views showing embodiments of the present invention; Figs. 4 and 5.
The figure is a diagram of part 11JF showing an embodiment of the present invention. 4... Core shroud, 6... Upper shroud, 7
...-fire heat exchanger, 11... fuel assembly, 12...
・Water surface, 13...downcomer pipe, 14...lower header,
15... Heat exchanger tube, 16... Ladder to the top, 17...
・Ascending pipe, 18... Kaya sweat track 3 Zuenaku 4 (21 Horse 5 (2) ↓1 Continued from page 1 0 Inventor Takeshi Sonoda 0 82 Watanabe-dori 2-1 Kaori, Chuo-ku, Fukuoka City No. Kyushu Electric Power Co., Inc. ■Out@Inventor Yoshinobu Takahashi 6-chome, Otemachi, Chiyoda-ku, Tokyo @No. 1 Inside Japan Atomic Power Co., Ltd. @Out@Inventor
Naoki Sakurama, 4-6, Kanda-Surugadai, Chiyoda-ku, Tokyo, Hitachi, Ltd. 0 Author: Kiyoshi Tsutsumi, 4-6, Kanda-Surugadai, Chiyoda-ku, Tokyo, Hitachi, Ltd., 4-6, Hitachi, Ltd. Author: Minoru Akita From Hitachi, Ltd., 41-6 Kanda Surugadai, Chiyoda-ku, Tokyo Applicant Tokyo Electric Power Co., Ltd. 1-1-3 Uchisaiwai-cho, Chiyoda-ku, Tokyo Applicant Hokkaido Electric Power Co., Inc. Sapporo City Chuo 1-2 Odori Higashi, Ward Applicant: Tohoku Electric Power Co., Ltd., 3-7-1, 1-cho, Sendai-shi Applicant: Chubu Electric Power Co., Inc., Higashishinmachi Ichiban, Higashi-ku, Nagoya City Applicant: Hokuriku Electric Power Co., Ltd., 3-1 Sakurabashi-dori, Toyama City Person: Kansai Electric Power Co., Ltd., 3-3-22 Nakanoshima, Osaka City, Japan. Person: Chugoku Electric Power Co., Inc., 4-33 Komachi, Naka-ku, Hiroshima City. Person: Shikoku Electric Power Co., Ltd., Takamatsu-type Hikari-no-uchi 2-5. Person: Kyushu Electric Power Co., Inc., Fukuoka. 2-1-82 Watanabe-dori, Chuo-ku, City Applicant Japan Atomic Power Co., Ltd. 6-1 Otemachi, Chiyoda-ku, Tokyo
Claims (1)
する原子炉圧力容器との間に、形成される自然循環下降
流路に配置された熱交換器において、円筒型配置直管伝
熱管群を原子炉圧力容器内円周方向に凹型短冊状に複数
分割して収納し、各々の伝熱管の上部および下部にヘッ
ダーを設け、二次冷却材の導出入管を全て原子炉圧力容
器の上部鏡板に集中配置し、その冷却材導出入管の原子
炉上部鏡板の貫通部において冷却材導出入管と鏡板の脱
着機構を設けることを％徴とする原子炉内に設置する熱
交換器。1. In a heat exchanger disposed in a natural circulation downflow path formed between a reactor core of a natural circulation reactor and a reactor pressure vessel housing this core, cylindrical straight heat exchanger tubes are used. The group is housed in a plurality of concave strips in the circumferential direction inside the reactor pressure vessel, and headers are provided at the top and bottom of each heat transfer tube, and all the secondary coolant inlet/output pipes are connected to the top of the reactor pressure vessel. A heat exchanger installed in a nuclear reactor, which is centrally arranged on the head plate, and has a mechanism for attaching and detaching the coolant inlet/output pipe and the head plate at the part where the coolant inlet/outlet pipe penetrates the head plate at the top of the reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58070557A JPS59195198A (en) | 1983-04-21 | 1983-04-21 | Heat exchanger installed in natural circulation type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58070557A JPS59195198A (en) | 1983-04-21 | 1983-04-21 | Heat exchanger installed in natural circulation type reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59195198A true JPS59195198A (en) | 1984-11-06 |
| JPH0358078B2 JPH0358078B2 (en) | 1991-09-04 |
Family
ID=13434944
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58070557A Granted JPS59195198A (en) | 1983-04-21 | 1983-04-21 | Heat exchanger installed in natural circulation type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59195198A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2007097293A1 (en) * | 2006-02-21 | 2007-08-30 | Mitsubishi Heavy Industries, Ltd. | Petrochemical complex |
| FR2985841A1 (en) * | 2012-01-18 | 2013-07-19 | Technicatome | SYSTEM FOR REMOVING THE RESIDUAL POWER OF A PRESSURIZED WATER NUCLEAR REACTOR |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58216985A (en) * | 1982-06-11 | 1983-12-16 | 株式会社東芝 | Bwr type reactor |
-
1983
- 1983-04-21 JP JP58070557A patent/JPS59195198A/en active Granted
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS58216985A (en) * | 1982-06-11 | 1983-12-16 | 株式会社東芝 | Bwr type reactor |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2007097293A1 (en) * | 2006-02-21 | 2007-08-30 | Mitsubishi Heavy Industries, Ltd. | Petrochemical complex |
| JP2007224058A (en) * | 2006-02-21 | 2007-09-06 | Mitsubishi Heavy Ind Ltd | Petrochemical complex |
| FR2985841A1 (en) * | 2012-01-18 | 2013-07-19 | Technicatome | SYSTEM FOR REMOVING THE RESIDUAL POWER OF A PRESSURIZED WATER NUCLEAR REACTOR |
| WO2013107817A1 (en) * | 2012-01-18 | 2013-07-25 | Societe Technique Pour L'energie Atomique Technicatome | System for discharging the residual power of a pressurised water nuclear reactor |
| CN104205238A (en) * | 2012-01-18 | 2014-12-10 | 原子能技术公司 | System for discharging the residual power of a pressurised water nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0358078B2 (en) | 1991-09-04 |
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