JPS59129301A - Nuclear power plant - Google Patents
Nuclear power plantInfo
- Publication number
- JPS59129301A JPS59129301A JP58001707A JP170783A JPS59129301A JP S59129301 A JPS59129301 A JP S59129301A JP 58001707 A JP58001707 A JP 58001707A JP 170783 A JP170783 A JP 170783A JP S59129301 A JPS59129301 A JP S59129301A
- Authority
- JP
- Japan
- Prior art keywords
- cooling system
- secondary cooling
- steam
- heat
- heat exchanger
- 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.)
- Pending
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
Landscapes
- Heat-Exchange Devices With Radiators And Conduit Assemblies (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】
本発明は原子カプラントに関する０
例えば、公知の高速増殖炉プラント（以下ＦＢＲという
）においては、第１図系統図１（テ示すように、原子炉
１で発生した熱を発電用としてタービン６へ伝えるため
に一次冷去０系。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear couplant. Primary cooling system for power generation to the turbine 6.
二次冷却系、水蒸気系の３系統がシリーズに設置され、
−次冷却系では、−次冷却材が原子炉１から出て、−次
冷却系配’Ｋｆ ’ ＋−次冷却系ポンプ；３および中
間熱交換器２を経由して原子炉１へ戻り、二次冷却系で
は、二次冷却材が中間熱交換器２内の伝熱管７において
一次冷却材から熱をもらい、二次冷却系配管１０、蒸気
発生器５．二次冷却系ポンプ４を経由して中間熱交換器
２へ戻り、水蒸気系ヤは、蒸気発生器５の伝熱管８で二
次冷却材から熱をもらい、水を蒸気に変え、発生した蒸
気が水、蒸気系配管１１を通りタービン６を介して発電
し、タービン６を出た蒸気がコンデンサ等を通って水に
なり、蒸気発生器５へ戻る。Three systems, a secondary cooling system and a steam system, are installed in series.
In the -secondary cooling system, the -secondary coolant leaves the reactor 1 and returns to the reactor 1 via the -secondary cooling system pump 3 and the intermediate heat exchanger 2, In the secondary cooling system, the secondary coolant receives heat from the primary coolant in the heat exchanger tubes 7 in the intermediate heat exchanger 2, and the secondary coolant receives heat from the secondary cooling system piping 10, steam generator 5. It returns to the intermediate heat exchanger 2 via the secondary cooling system pump 4, and the steam system receives heat from the secondary coolant through the heat transfer tubes 8 of the steam generator 5, converts water into steam, and generates steam. The water passes through the steam system piping 11 and generates electricity via the turbine 6, and the steam exiting the turbine 6 passes through a condenser and the like to become water and returns to the steam generator 5.
しかしながら、このようなプラントにおいては、上記各
系統のうち二次冷却系は、主として安全上の理由から設
置されておシ、中間熱交換器２は放射線管理区域内に設
置され、蒸気発生器５は非管理区域に設置され、両者は
あまり近接しておらず、捷だ、遮蔽放射線上および配管
の応力緩和上から二次冷却系配管Ｉ Ｃ＋ ４：ｌ、長
大なものどなり、配管からの放÷１１熱ｆｉ、も多く、
才だ全体として系、枕が複雑に々っている。However, in such plants, among the above systems, the secondary cooling system is installed mainly for safety reasons, the intermediate heat exchanger 2 is installed in the radiation controlled area, and the steam generator 5 is installed in the radiation control area. The secondary cooling system piping is installed in an uncontrolled area, and the two are not very close to each other. ÷11 heat fi, too many,
Overall, the system and pillows are complicated.
本発明はこのような事情に鑑みて提案されたもので、二
次冷却系を簡素化し、二次冷却系からの熱放散を減少し
て熱効率を高めるとともにプラントの制御を簡単にし、
安全性を向上するプラントを提供することを目的とし、
−次冷却系と、上記−次冷却系と熱交換する二次冷却系
と、上記二次冷却系と熱交換する水、蒸気系との３循環
系統を有する原子カプラントにおいて、上記−次冷却系
と二次冷却系との熱交換を行なう容器内に上記二次冷却
系と水、蒸気系との熱交換を行なう二重管を内蔵してな
る共用型熱交換器を具えたことを特徴とする。The present invention was proposed in view of these circumstances, and it simplifies the secondary cooling system, reduces heat dissipation from the secondary cooling system, increases thermal efficiency, and simplifies plant control.
Our aim is to provide plants that improve safety.
In an atomic coupler having three circulation systems: - a secondary cooling system, a secondary cooling system that exchanges heat with the secondary cooling system, and a water and steam system that exchanges heat with the secondary cooling system, the secondary cooling system and a shared type heat exchanger having a built-in double pipe for exchanging heat between the secondary cooling system and the water and steam system inside the container for exchanging heat between the secondary cooling system and the water and steam system. do.
本発明の一実施例を図面について説明すると、第２図は
その系統図、第３図は第２図の共用熱交換器の二重管を
示す拡大横断面図である。An embodiment of the present invention will be described with reference to the drawings. FIG. 2 is a system diagram thereof, and FIG. 3 is an enlarged cross-sectional view showing a double pipe of the shared heat exchanger of FIG. 2.
Ｆ図において、第１図吉同−の記刊はそれぞれ同図と同
一の機器２部材を示し、１２は一次冷却系から水、蒸気
系への伝熱のために設けられた中間熱交換兼蒸気発生共
用型熱交換器（以下共用型熱交換器という）である。In Fig. F, the entries in Fig. 1 Kichido indicate two parts of equipment that are the same as those in the same drawing, and 12 is an intermediate heat exchanger and an intermediate heat exchanger provided for heat transfer from the primary cooling system to the water and steam systems. This is a steam generation shared heat exchanger (hereinafter referred to as a shared heat exchanger).
共用型熱交換器１２には二重管１３が貫通内蔵され、二
重管のうち外管１８の外側１７には一次冷却部材が、外
管１８と内管２ｏの環状間隙１９には二次冷却材が、内
管２ｏの内側２１には水又は蒸気がそれぞれ流れ、二重
管１３の形状は直管であっても、またスパイラル、Ｕ字
形そｌの他の形状でもよく、また、その内部に一次冷却
拐、外部に水、蒸気があってもよい。The shared heat exchanger 12 has a double pipe 13 penetrating therethrough, and a primary cooling member is provided on the outside 17 of the outer pipe 18 of the double pipe, and a secondary cooling member is provided in the annular gap 19 between the outer pipe 18 and the inner pipe 2o. The coolant flows through the inner side 21 of the inner pipe 2o, and the shape of the double pipe 13 may be a straight pipe, a spiral, a U-shape, or other shapes. There may be primary cooling inside and water or steam outside.
また、共用型熱交換器１２の近傍に二次冷却系新配管１
５および膨張タンク１４が、さらに、必要に応じて二次
冷却系循環ポンプ１６がそれぞれ設置されて、二次冷却
系を構成し、二次冷却系には、伝熱管破損を検出する機
器を設けてもよい。こ＼で一般に一次冷却イ７１．二次
冷却利は、ぞ１１ぞｊ＋ Ｎ ａ等のアルカリ金属であ
る。In addition, new piping 1 for the secondary cooling system is installed near the shared heat exchanger 12.
5 and the expansion tank 14, and a secondary cooling system circulation pump 16 is installed as necessary to form a secondary cooling system, and the secondary cooling system is equipped with a device for detecting damage to the heat transfer tubes. It's okay. This is generally the primary cooling step71. The secondary cooling rate is an alkali metal such as 11 zo j + Na.
このＪ：うなプラントにおいて、−次冷却材は、共用型
熱交換３％１２の内部において伝熱管１；３のうち外管
１８を介して二次冷却材と熱交換を行ない、また二次冷
却材は内管２０を介して水、蒸気と熱交換を行なう。In this J: Una plant, the secondary coolant exchanges heat with the secondary coolant inside the shared heat exchanger 3% 12 through the outer tube 18 of the heat transfer tubes 1; The material exchanges heat with water and steam through the inner tube 20.
二次冷却祠の熱による体積変化は、二次冷却系新配管１
５を通して膨張タンク１４にムリ吸収される。The change in volume due to heat in the secondary cooling shrine is due to the new piping 1 of the secondary cooling system.
5 and is absorbed into the expansion tank 14.
また必要に応じて、二次冷却系循環ポンプ１６を設置し
、二次冷却材の循環を行なうことに」：り伝熱効率を上
昇させる。Furthermore, if necessary, a secondary cooling system circulation pump 16 is installed to circulate the secondary coolant, thereby increasing the heat transfer efficiency.
このようなプラントによれば、プラントとじての熱放散
が少々く々るので、熱効率が良くなり、経済性を増し、
二次冷却系の簡素化によりプラントの制御が容易になる
ため安全性を向上し、二次冷却系の機器、配管、用益。According to such a plant, heat dissipation throughout the plant is a little slow, so thermal efficiency is improved, economical efficiency is increased,
The simplification of the secondary cooling system makes it easier to control the plant, improving safety and improving the equipment, piping, and utility of the secondary cooling system.
関連諸設備等を大幅に削減すると＼もに建屋を小さくし
、二次冷却材の容情が減少し、配置」二モコンバクト（
・・−なるので、冷却４］として危険物を使用する場合
、安全管理上有利となる。Significantly reducing the number of related equipment will also reduce the size of the building, reduce the amount of secondary coolant, and improve the layout of the building.
. . . Therefore, when using dangerous materials as cooling 4], it is advantageous in terms of safety management.
要するに本発明によれば、−次冷却系と、上記−次冷却
系と熱交換する二次冷却系と、上記二次冷却系と熱交換
する水、蒸気系との３循環系統を有する原子カプラント
において、上記−次冷却系と二次冷却系との熱交換を行
なう容器内に上記二次冷却系と水、蒸気系との熱交換を
行なう二重管を内蔵してなる共用型熱交換器を具えたこ
とにより、安全性および経済性の高い原子カプラントを
得るから、本発明は産業上極めて有益なものである。In short, according to the present invention, an atomic coupler has three circulation systems: a secondary cooling system, a secondary cooling system that exchanges heat with the secondary cooling system, and a water and steam system that exchanges heat with the secondary cooling system. A shared heat exchanger comprising a double pipe for exchanging heat between the secondary cooling system and the water or steam system inside a container for exchanging heat between the secondary cooling system and the water or steam system. The present invention is industrially extremely useful because it provides an atomic couplant with high safety and economic efficiency.
第１図は公知の高速増殖炉プラントを示す系統図、第２
図は本発明の一実施例を示す系統図、第３図は第２図の
共用熱交換器の二重管を示す拡大横断面図である。
１・・原子炉、：３・・−次冷却系ポンプ、６・・ター
ビン、９・・−次冷却系配管、１１・・水。
依気系配管、１２・・共用１型熱交換器、１３・・二重
管、１・１・・膨張タンク、１５・・二次冷却系新船・
管、１６・・二次冷却系循環ポンプ、１７・・外側、１
８・・外管、１９・・間隙、２０・・内管、２１・・内
側、
復代理人 弁理士 塚 本 正 文Figure 1 is a system diagram showing a known fast breeder reactor plant;
The figure is a system diagram showing one embodiment of the present invention, and FIG. 3 is an enlarged cross-sectional view showing a double pipe of the shared heat exchanger of FIG. 2. 1... Nuclear reactor, 3... Secondary cooling system pump, 6... Turbine, 9... Secondary cooling system piping, 11... Water. Air system piping, 12. Common type 1 heat exchanger, 13. Double pipe, 1.1. Expansion tank, 15. Secondary cooling system for new ship.
Pipe, 16...Secondary cooling system circulation pump, 17...Outside, 1
8...Outer pipe, 19...Gap, 20...Inner pipe, 21...Inside, Sub-Agent Masafumi Tsukamoto, Patent Attorney
Claims (1)
と、」ユ記二次冷却系と熱交換する水、蒸気系との３循
環系統を有する原子カプラントにおいて、上詰−次冷却
系と二次冷却系との熱交換を行なう容器内に手記二次冷
却系と水蒸気系との熱交換を行なう二重管を内蔵してな
る共用型熱交換器を具えたことを特徴とする原子カプラ
ント０In an atomic coupler plant that has three circulation systems: a primary cooling system, a secondary cooling system that exchanges heat with the above-mentioned secondary cooling system, and a water and steam system that exchanges heat with the secondary cooling system, It is characterized by being equipped with a shared type heat exchanger that has a built-in double tube for exchanging heat between the secondary cooling system and the steam system inside the container that exchanges heat between the cooling system and the secondary cooling system. atomic couplant 0
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58001707A JPS59129301A (en) | 1983-01-11 | 1983-01-11 | Nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58001707A JPS59129301A (en) | 1983-01-11 | 1983-01-11 | Nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59129301A true JPS59129301A (en) | 1984-07-25 |
Family
ID=11509018
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58001707A Pending JPS59129301A (en) | 1983-01-11 | 1983-01-11 | Nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59129301A (en) |
-
1983
- 1983-01-11 JP JP58001707A patent/JPS59129301A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104321825A (en) | Pressurized water reactor compact steam generator | |
| JPH0216496A (en) | Isolation condenser with stop cooling system heat exchanger | |
| US4407773A (en) | Nuclear reactor installation | |
| JPS639889A (en) | Nuclear power device | |
| US5114667A (en) | High temperature reactor having an improved fluid coolant circulation system | |
| JPS62185192A (en) | Nuclear reactor pressure vessel | |
| JPS59129301A (en) | Nuclear power plant | |
| US4257356A (en) | Heat exchanging apparatus and method | |
| US5335252A (en) | Steam generator system for gas cooled reactor and the like | |
| US5047204A (en) | Nuclear fuel element for a particle bed reactor | |
| RU208763U1 (en) | heat exchanger | |
| GB955844A (en) | ||
| GB1242533A (en) | Improvements in or relating to nuclear reactors | |
| JPH0547965Y2 (en) | ||
| JPS6027895A (en) | Fast breeder reactor | |
| JPH0814634B2 (en) | Distributed reactor | |
| JPH033830Y2 (en) | ||
| Young et al. | A Plant with Water Cooling | |
| JPS5623667A (en) | Heat accumulator for solar heat cooling and heating | |
| GB1243371A (en) | Improvements in or relating to nuclear reactors | |
| JPH0446321B2 (en) | ||
| JPS63127192A (en) | Fast breeder reactor plant | |
| JPS6049293A (en) | Cooling device for cooling system installed to rear section of high-temperature gas furnace | |
| JPH0252240B2 (en) | ||
| JPS63127188A (en) | Tank type fast breeder reactor |