JPH02222892A - Heating device of condensate storage tank - Google Patents
Heating device of condensate storage tankInfo
- Publication number
- JPH02222892A JPH02222892A JP1011891A JP1189189A JPH02222892A JP H02222892 A JPH02222892 A JP H02222892A JP 1011891 A JP1011891 A JP 1011891A JP 1189189 A JP1189189 A JP 1189189A JP H02222892 A JPH02222892 A JP H02222892A
- Authority
- JP
- Japan
- Prior art keywords
- rcw
- storage tank
- condensate
- condensate storage
- water
- 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
- 238000010438 heat treatment Methods 0.000 title claims abstract description 30
- 238000001816 cooling Methods 0.000 claims abstract description 14
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 31
- 239000013535 sea water Substances 0.000 abstract description 4
- 238000011109 contamination Methods 0.000 abstract description 2
- 230000002265 prevention Effects 0.000 abstract 1
- 230000002285 radioactive effect Effects 0.000 description 4
- 239000012530 fluid Substances 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 2
- 238000009835 boiling Methods 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 239000008213 purified water Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は原子力発電プラントに設置されている復水貯蔵
タンクの加熱装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a heating device for a condensate storage tank installed in a nuclear power plant.
（従来の技術）
沸騰水型原子力発電プラントではタービンで仕事を終え
た蒸気を主復水器で復水し、この復水をろ過器および脱
塩器を通して純化し、この純化した水を給水加熱器で加
熱し、給水管から原子炉圧力容器へ流入する配管経路を
有している。この経路のうち、復水脱塩器の出口側から
分岐した復水の一部を復水貯蔵タンク内へ流入する経路
を設けている。この復水貯蔵タンク内に貯蔵された水は
所定の温度に加熱されて制御棒駆動系ないしは原子炉補
機冷却系などへ送られる。(Prior art) In a boiling water nuclear power plant, the steam that has finished its work in the turbine is condensed in the main condenser, the condensed water is purified through a filter and a demineralizer, and the purified water is heated for feed water. It has a piping route that is heated by the reactor and flows from the water supply pipe to the reactor pressure vessel. Among these routes, a route is provided in which a part of the condensate branched from the outlet side of the condensate demineralizer flows into the condensate storage tank. The water stored in this condensate storage tank is heated to a predetermined temperature and sent to the control rod drive system or reactor auxiliary equipment cooling system.
従来の復水貯蔵タンク内の水は原子力発電プラント内の
加熱蒸気系Ｈ８からの熱によって加熱されている。すな
わち、この加熱装置は第５図および第６図に示したよう
に復水貯蔵タンク１内に加熱コイル２を設置し、この加
熱コイル２に空気弁３を接続し、この空気弁３の流入側
に加熱蒸気系Ｈ８の配管を接続してなるものである。な
お、第６図は第５図のＡ−Ａ矢視方向を切断して示す横
断面図であり、図中符号４は復水戻すライン、５は給水
ライン、６は加熱コイル２のサポート、７は温度コント
ローラをそれぞれ示している。The water in conventional condensate storage tanks is heated by heat from the heating steam system H8 in the nuclear power plant. That is, in this heating device, as shown in FIGS. 5 and 6, a heating coil 2 is installed in a condensate storage tank 1, an air valve 3 is connected to this heating coil 2, and the inflow of A heating steam system H8 piping is connected to the side. In addition, FIG. 6 is a cross-sectional view taken in the direction of the arrow A-A in FIG. 7 indicates a temperature controller.
このように加熱蒸気系Ｈ３からの蒸気によって復水貯蔵
タンク１内の水を加熱している。この装置では温度コン
トローラ７によりタンク１内の水温を監視し、空気弁３
を開閉することによってタンク１内の水温を一定に保持
することができる。In this way, the water in the condensate storage tank 1 is heated by the steam from the heating steam system H3. In this device, the temperature controller 7 monitors the water temperature in the tank 1, and the air valve 3
By opening and closing the water temperature in the tank 1 can be kept constant.
加熱蒸気系（Ｈ５）は原子力発電プラント内の負荷を加
熱するための系統つまり、ニーテリティであって、蒸気
配管および供給圧力を制御するための減圧弁などで構成
されている。The heating steam system (H5) is a system for heating the load in the nuclear power plant, that is, a neuterity, and is composed of steam piping, a pressure reducing valve for controlling the supply pressure, and the like.
（発明が解決しようとする課題）
加熱蒸気系Ｈ８は原子炉建屋（Ｒ／ Ｂ ） ｐタービ
ン建屋（Ｔ／Ｂ）、サービス建屋（Ｓ／Ｂ）などの内外
に設置される諸設備に補助ボイラから発生する蒸気を供
給する。補助ボイラで発生した蒸気は各機器へ蒸気配管
を介して供給される。加熱蒸気系はクリーンな系統であ
り、補助ボイラ設備などはクリーンな区域に設置されて
いるため、加熱蒸気は汚染されてはならないものなので
ある。(Problem to be solved by the invention) The heating steam system H8 is equipped with an auxiliary boiler in various facilities installed inside and outside the reactor building (R/B), p-turbine building (T/B), service building (S/B), etc. supply the steam generated from the Steam generated in the auxiliary boiler is supplied to each device via steam piping. The heating steam system is a clean system, and the auxiliary boiler equipment is installed in a clean area, so the heating steam must not be contaminated.
しかしながら、復水貯蔵タンク１内の加熱コイル２に加
熱蒸気を通しているため、加熱コイル２にピンホール亀
裂などが発生してリークが生じた場合、加熱蒸気が汚染
されることになる。また、加熱蒸気系は閉ループの系統
でないため、復水貯蔵タンク１まで配管を封殺すること
が容易ではなく、シたがって系統容量の増大につながっ
ている。さらに、空気弁を使用しているため、空気配管
をプラント内から屋外に設置されている復水貯蔵タンク
まで封殺しなくてはならないことになる。However, since heated steam is passed through the heating coil 2 in the condensate storage tank 1, if a pinhole crack or the like occurs in the heating coil 2 and a leak occurs, the heated steam will be contaminated. Furthermore, since the heating steam system is not a closed loop system, it is not easy to seal off the piping up to the condensate storage tank 1, which leads to an increase in system capacity. Furthermore, since air valves are used, the air piping must be sealed off from inside the plant to the condensate storage tank installed outdoors.
本発明は上記課題を解決するためになされたもので、加
熱蒸気の汚染を防止し、かつ加熱蒸気系および空気系の
系統容量を削減し、復水貯蔵タンク内の水を一定温度以
上に保つことができる復水貯蔵タンクの加熱装置を提供
することにある。The present invention was made to solve the above problems, and it prevents heating steam from being contaminated, reduces the system capacity of the heating steam system and air system, and maintains the water in the condensate storage tank above a certain temperature. An object of the present invention is to provide a heating device for a condensate storage tank.
（課題を解決するための手段）
本発明は復水貯蔵タンク内に原子炉補機冷却系の戻り配
管を設けてなることを特徴とする。(Means for Solving the Problems) The present invention is characterized in that a return pipe for a reactor auxiliary equipment cooling system is provided in a condensate storage tank.
（作 用）
復水は蔵タンク内の水は原子炉補機冷却系戻り配管内を
流れる戻り水で常に加熱されるため一定温度以上に保持
される。加熱蒸気が流れないのでその加熱蒸気が汚染す
ることがない。(Function) The water in the storage tank is constantly heated by the return water flowing through the reactor auxiliary cooling system return piping, so it is maintained above a certain temperature. Since heating steam does not flow, the heating steam does not become contaminated.
（実施例）
第１図および第２図を参照しながら本発明に係る復水貯
蔵タンクの加熱装置の一実施例を説明する。(Embodiment) An embodiment of a heating device for a condensate storage tank according to the present invention will be described with reference to FIGS. 1 and 2.
第１図において、復水貯蔵タンク１内に原子炉補機冷却
系（ＲＣＷ）から仕切弁８を介してＲＣＷ戻り配管９を
設け、この戻り配管９をサポート６で支持固定する。復
水貯蔵タンク１には戻りライン４が接続されており、こ
の戻りライン４により復水が戻され、給水ライン５によ
り復水貯蔵ライン１から復水を供給する。ＲＣＷ戻り配
管９は第３図および第４図に示したように配管９の外面
に保護管１０を設けることもできる。In FIG. 1, an RCW return pipe 9 is provided in a condensate storage tank 1 from a reactor auxiliary cooling system (RCW) via a gate valve 8, and this return pipe 9 is supported and fixed by a support 6. A return line 4 is connected to the condensate storage tank 1, through which condensate is returned, and through a water supply line 5, condensate is supplied from the condensate storage line 1. The RCW return pipe 9 can also be provided with a protection pipe 10 on the outer surface of the pipe 9, as shown in FIGS. 3 and 4.
復水貯蔵タンク１内の水はＲＣＷ戻り配管９内を流れる
ＲＣＷ戻り水によって常に加熱され、定温度以上に保つ
ことができる。The water in the condensate storage tank 1 is constantly heated by the RCW return water flowing in the RCW return pipe 9 and can be kept at a constant temperature or higher.
原子炉補機冷却系（ＲＣＷ）は原子炉建屋（Ｒ／Ｂ）内
に設けられている非常用機器、残留熱除去系機器、原子
炉常用補機、廃棄物処理系機器およびタービン建Ｍ （
Ｔ／Ｂ）内の放射性流体を取扱う補機を冷却するための
系統で、閉ループであり、ＲＣＷポンプ、ＲＣＷ熱交換
器、冷却対象機器、配管などからなっている。冷却対象
機器を冷却したのち、戻り水はＲＣＷポンプにより加熱
され、ＲＣＷ熱交換器で海水により冷却される。ＲＣＷ
熱交換器でＲＣＷ水を冷却するのは原子炉補機冷却海水
系（ＲＳＷ）である。The reactor auxiliary cooling system (RCW) is a system installed in the reactor building (R/B) that includes emergency equipment, residual heat removal system equipment, reactor regular auxiliary equipment, waste treatment system equipment, and turbine building M (
This is a closed loop system for cooling auxiliary equipment that handles radioactive fluid in the T/B), and consists of an RCW pump, an RCW heat exchanger, equipment to be cooled, piping, etc. After cooling the equipment to be cooled, the return water is heated by the RCW pump and cooled by seawater in the RCW heat exchanger. R.C.W.
The reactor auxiliary cooling seawater system (RSW) cools the RCW water using a heat exchanger.
ＲＣＷは元々放射性流体を取扱う機器を冷却しており、
万が一汚染された場合を考慮して冷却水母管に放射線モ
ニタを設けている。RCW was originally used to cool equipment that handles radioactive fluids.
A radiation monitor is installed on the cooling water main pipe in case it becomes contaminated.
放射性流体を取扱う機器（ＣＳＴを含む）でリーク（も
れ）があり、ＲＣＷが汚染されたとしても、上記放射性
モニタにより、それを検知してＲＣＷを全停とするので
、環境（海水等）に放射性物質が流入することはない。Even if there is a leak in equipment that handles radioactive fluids (including CST) and the RCW is contaminated, the radioactive monitor will detect it and completely shut down the RCW, so the environment (seawater, etc.) No radioactive materials will flow into the area.
ここで、空気弁３と仕切弁８との相違について説明する
と、空気弁３は圧縮空気によって作動する弁を指してお
り、仕切り弁８は弁の種類（ｔｙｐｅ）を表している。Here, to explain the difference between the air valve 3 and the gate valve 8, the air valve 3 refers to a valve operated by compressed air, and the gate valve 8 represents the type of valve.
また、ＲＣＷ戻り水によって復水貯蔵タンク１内の水が
常に一定に保てる理由は１１０万ＫＷＲｆｉ子力発電所
（Ｂプラント）を例にとって確認してみるとつぎのとう
りである。Further, the reason why the water in the condensate storage tank 1 can always be kept constant by the RCW return water is as follows when confirmed by taking a 1.1 million KWRfi child power plant (Plant B) as an example.
ＲＣＷ戻り水
流量：通常運転時、定検時、・・・等複数の運転モード
の中で最も少ないとき（通
常運転時）で約１１００耐／ｈ
温度： ＲＣＷ冷却水温度は温度調節弁により３０℃前
後に調節されている。また、通常運転時の交換熱量（各
冷却対象
機器の和）は約１．Ｉ Ｘ １０７ｋｃａＱよって、
Δｔ＝ ＬＩＸＩＯ７／ １１００ （ｋｃａＱ／ｍ
”）押１０ ［７２／ζ］押１０ （”Ｃ）従って、Ｒ
ＣＷの戻り水温塵は
ｔ ＝ ３０ ＋ １０ ＝ ４０ （’Ｃ）０ 復水
貯蔵タンク内の水
容量：ＭａＸ３０００ｍ３
温度１０℃のときに、ｘｒｒｒのＲＣＷ戻り水で加熱す
るとすると。RCW return water flow rate: Approximately 1100 withstand/h at the lowest among multiple operating modes (normal operation) such as during normal operation, periodic inspection, etc. Temperature: RCW cooling water temperature is adjusted to 30% by temperature control valve. It is regulated around ℃. Also, the amount of heat exchanged during normal operation (sum of each cooling target device) is approximately 1. According to I x 107kcaQ,
Δt= LIXIO7/ 1100 (kcaQ/m
”) Press 10 [72/ζ] Press 10 (”C) Therefore, R
CW return water temperature dust is t = 30 + 10 = 40 ('C)0 Water capacity in condensate storage tank: MaX 3000 m3 Suppose that when the temperature is 10°C, heating is done with xrrr of RCW return water.
以上から復水貯蔵タンク内の水を１０℃以上に保つため
にはＲＣＷ戻り水のうちの何割かをバイパスさせて復水
貯蔵タンクに通せばよい。From the above, in order to maintain the water in the condensate storage tank at 10° C. or higher, it is sufficient to bypass some of the RCW return water and pass it through the condensate storage tank.
本発明によれば復水貯蔵タンク内の水を一定温度以上に
保ち、加熱蒸気汚染の可能性を除去することができる。According to the present invention, it is possible to maintain the water in the condensate storage tank above a certain temperature and eliminate the possibility of heating steam contamination.
また、加熱蒸気、空気系の系統容量を削減することがで
き、コスト低減に寄与することができる。Furthermore, the capacity of the heating steam and air systems can be reduced, contributing to cost reduction.
第１図は本発明に係る復水貯蔵タンクの加熱装置の一実
施例を一部概略的に示す縦断面図、第２図は第１図のｎ
−ｎ線に沿って切断して示す横断面図、第３図は第１図
における配管系を一部断面で示す側面図、第４図は第３
図のＩＶ−ＩＶ線に沿って切断して示す縦断面図、第５
図は従来の復水貯蔵タンクの加熱装置を一部概略的に示
す縦断面図、第６図は第５図のＶＩ−ＶＩ線に沿って示
す横断面図である。
１・・・復水貯蔵タンク、 ２・・・加熱コイル。
３・・・空気弁、 ４・・・戻りライン、５
・・・給水ライン、 ６・・・サポート、７・・
・温度コントローラ、８・・・仕切弁、９・・・ＲＣＷ
戻り配管、 １０・・・保護管。
（８７３３）代理人弁理士 猪 股 祥 晃（ほか１名
）茅
面
茅
乙
図FIG. 1 is a vertical sectional view partially schematically showing an embodiment of a heating device for a condensate storage tank according to the present invention, and FIG.
3 is a side view showing a partial cross section of the piping system in FIG.
Vertical sectional view taken along line IV-IV in the figure, No. 5
The figure is a vertical cross-sectional view partially schematically showing a conventional heating device for a condensate storage tank, and FIG. 6 is a cross-sectional view taken along line VI-VI in FIG. 1... Condensate storage tank, 2... Heating coil. 3...Air valve, 4...Return line, 5
...Water supply line, 6...Support, 7...
・Temperature controller, 8...Gate valve, 9...RCW
Return piping, 10... protection pipe. (8733) Representative Patent Attorney Yoshiaki Inomata (and 1 other person) Kayamen Kayotsu
Claims (1)
てなることを特徴とする復水貯蔵タンクの加熱装置。A heating device for a condensate storage tank, characterized in that a return pipe for a reactor auxiliary cooling system is provided in the condensate storage tank.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1011891A JPH02222892A (en) | 1989-01-23 | 1989-01-23 | Heating device of condensate storage tank |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1011891A JPH02222892A (en) | 1989-01-23 | 1989-01-23 | Heating device of condensate storage tank |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH02222892A true JPH02222892A (en) | 1990-09-05 |
Family
ID=11790352
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1011891A Pending JPH02222892A (en) | 1989-01-23 | 1989-01-23 | Heating device of condensate storage tank |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH02222892A (en) |
-
1989
- 1989-01-23 JP JP1011891A patent/JPH02222892A/en active Pending
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