JPS5834395A - Reactor coolant cleaning device - Google Patents
Reactor coolant cleaning deviceInfo
- Publication number
- JPS5834395A JPS5834395A JP56132718A JP13271881A JPS5834395A JP S5834395 A JPS5834395 A JP S5834395A JP 56132718 A JP56132718 A JP 56132718A JP 13271881 A JP13271881 A JP 13271881A JP S5834395 A JPS5834395 A JP S5834395A
- Authority
- JP
- Japan
- Prior art keywords
- water supply
- reactor
- heat exchanger
- temperature
- piping
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Cleaning By Liquid Or Steam (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、沸騰水型原子力発電プラントにおける原子炉
冷却材浄化装置に係り、特に原子炉の給水配管およびノ
ズルの熱疲労の低減を図る浄化系統に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a reactor coolant purification system in a boiling water nuclear power plant, and more particularly to a purification system for reducing thermal fatigue of water supply pipes and nozzles of a nuclear reactor.
従来の浄化系統は、温度制御ができないために原子炉の
起動時に給水が開始されていない場合、給水配管は、浄
化系からの戻り温度により加熱さく１）
れた状態にあり、加熱されていない給水が開始された時
に大きな熱衝撃を受ける。前記現象が、原子炉運転期間
中に繰り返えされるために給水配管およびノズルに過大
の熱疲労を考慮する必要がある。また、原子炉が隔離さ
れた時も、給水が加熱されずに間欠運転されるため、前
記と同様な現象が生じる。In conventional purification systems, if water supply is not started at the time of reactor startup because temperature control is not possible, the water supply piping remains heated due to the return temperature from the purification system and is not heated. When water supply starts, it receives a large thermal shock. Since the above phenomenon is repeated during the operating period of the nuclear reactor, it is necessary to consider excessive thermal fatigue of the water supply piping and nozzles. Furthermore, even when a nuclear reactor is isolated, the same phenomenon as described above occurs because the feed water is not heated and is operated intermittently.
本発明の目的は、前記給水配管・ノズルの熱疲労の原因
となる前記浄化系統の再熱用熱交換器の出口温度の良好
な制御および運転方法を提供することにある。An object of the present invention is to provide a good control and operation method for the outlet temperature of the reheat heat exchanger of the purification system, which causes thermal fatigue of the water supply pipes and nozzles.
本発明は、給水配管とノズルの熱疲労が、原子炉の起動
時および隔離時の加熱されていない給水温度と加熱され
た浄化系統温度の差による繰り返し応力によって生じる
ことに着目し、この温度差を解消する手段として、浄化
系統の再熱用熱交換器を通さないバイパスラインと前記
熱交換器の出口およびバイパスラインに制御弁を設けて
浄化系統の温度を給水温度と同じにすることにより、給
水配管・ノズルの熱疲労を防止したものである。The present invention focuses on the fact that thermal fatigue of water supply piping and nozzles is caused by repeated stress due to the difference between the temperature of the unheated feed water and the heated purification system temperature during reactor startup and isolation. As a means to eliminate this problem, a bypass line that does not pass through the reheat heat exchanger of the purification system, and a control valve at the outlet of the heat exchanger and the bypass line are provided to make the temperature of the purification system the same as the water supply temperature. This prevents thermal fatigue of water supply piping and nozzles.
（２）− 以下、本発明の一実施例を第１図により説明する。(2)- An embodiment of the present invention will be described below with reference to FIG.
原子炉１より取り出された水は、ポンプ２により加圧さ
れ、再生熱交換器２および非再生熱交換器３により冷却
された後、濾過脱塩装置により浄化され、再生熱交換器
３により再び加熱され、給水配管８を経由して原子炉１
に戻る。Water taken out from the reactor 1 is pressurized by a pump 2, cooled by a regenerative heat exchanger 2 and a non-regenerative heat exchanger 3, purified by a filtration desalination device, and then recycled by a regenerative heat exchanger 3. It is heated and sent to the reactor 1 via the water supply pipe 8.
Return to
起動時には、原子炉が昇温されるに伴ない、浄化系統の
配管６の流体温度も上昇する。原子炉１が十分に昇温さ
れるまで給水は開始されないため、給水配管８およびノ
ズル９は、浄化系統の戻り温度のために加熱された状態
にある。原子炉が十分な圧力に達しだ時に、給水は開始
されるが、タービンからの抽気がないために、給水は加
熱されずに冷温のまま原子炉１に供給される。この時に
配管８は、大きな熱衝撃を受けることになる。At startup, as the temperature of the nuclear reactor increases, the temperature of the fluid in the piping 6 of the purification system also increases. Since water supply is not started until the reactor 1 is sufficiently heated, the water supply pipe 8 and nozzle 9 are in a heated state due to the return temperature of the purification system. When the reactor reaches sufficient pressure, water supply is started, but since there is no bleed air from the turbine, the feed water is not heated and is supplied to the reactor 1 at a cold temperature. At this time, the pipe 8 will receive a large thermal shock.
本発明では、再生熱交換器３にパイ・くス配管７と制御
弁１２を設け、また再生熱交換器出口配管６にも制御弁
を設け、２つの制御弁を連動することにより、配管１０
の流量を一定としたまま、温度制御ができる。以下、原
子炉の起動時の運転方法を説明する。In the present invention, the regenerative heat exchanger 3 is provided with the pipe 7 and the control valve 12, and the regenerative heat exchanger outlet pipe 6 is also provided with a control valve, and by interlocking the two control valves, the piping 10
The temperature can be controlled while keeping the flow rate constant. The operating method at startup of the nuclear reactor will be explained below.
原子炉が十分な圧力に達する捷では、弁１２を開とし、
弁１１を閉とすることにより、原子炉１に冷水を供給す
る。加熱されない給水が開始された後、タービンからの
抽気が行なわれ給水が加熱される時に、給水加熱器出口
温度と弁１１．弁１２とを連動させ、弁１１を開、弁１
２を閉にすることにより、給水温度に追従させる。When the reactor reaches sufficient pressure, valve 12 is opened,
By closing the valve 11, cold water is supplied to the reactor 1. After the unheated feed water is started, the feed water heater outlet temperature and valve 11. Valve 12 is linked to open valve 11, and valve 1 is opened.
By closing 2, it follows the temperature of the water supply.
本発明によれば、第２図と第３図に示すような効果があ
る。第２図および第３図は、給水ノズルおよびそれに接
続する配管の温度変化を示す。According to the present invention, there are effects as shown in FIGS. 2 and 3. FIGS. 2 and 3 show temperature changes in the water supply nozzle and the piping connected thereto.
第２図は、従来の給水ノズルおよび配管の温度変化であ
り、区間２１−２２は、浄化系統により加熱される温度
変化、区間２２−２３は、給水が供給されるために冷却
される温度変化、区間２３−２４は、加熱されない給水
が供給される区間、区間２４−２５−．２６は、給水が
加熱される区間を示す。FIG. 2 shows the temperature change of the conventional water supply nozzle and piping, where the section 21-22 shows the temperature change as it is heated by the purification system, and the section 22-23 shows the temperature change as the water supply is cooled. , sections 23-24 are sections where unheated water is supplied, sections 24-25-. 26 indicates the section where the feed water is heated.
第３図は、本発明により改善された給水ノズルおよび配
管の温度変化を示す。第３図は、第２図の区間１−２−
３が解消されている。このことは、原子炉プラント運転
中に数十回にわたり行なわれる起動時の給水ノズルおよ
び配管の温度変化の繰り返しを緩和でき、給水ノズルお
よび配管の使用条件を緩和でき、クラック等の発生要因
をなくせる。FIG. 3 shows the temperature change of the water supply nozzle and piping improved by the present invention. Figure 3 shows section 1-2- in Figure 2.
3 has been resolved. This can alleviate the repeated temperature changes of the water supply nozzle and piping during startup, which occur dozens of times during reactor plant operation, ease the usage conditions for the water supply nozzle and piping, and eliminate the causes of cracks, etc. let
第１図は本発明による原子炉冷却材浄化装置の系統図、
第２図は従来の給水ノズルおよび配管の温度変化図、第
３図は本発明による給水ノズルおよび配管の温度変化図
である。
１・・・原子炉、２・・・循環ポンプ、３・・・再生熱
交換器、４・・・非再生熱交換器、５・・・濾過脱塩装
置、６．７゜第１ 目FIG. 1 is a system diagram of a reactor coolant purification system according to the present invention;
FIG. 2 is a temperature change diagram of a conventional water supply nozzle and piping, and FIG. 3 is a temperature change diagram of a water supply nozzle and piping according to the present invention. 1... Nuclear reactor, 2... Circulation pump, 3... Regenerative heat exchanger, 4... Non-regenerative heat exchanger, 5... Filtration desalination device, 6.7° 1st
Claims (1)
ポンプにより供給する給水装置と原子炉より取り出され
た水を熱交換器により冷却した後、ろ過脱塩装置により
浄化し、熱交換器にて再び加熱して前記給水装置を経由
して原子炉に戻す浄化装置において、前記浄化装置の再
熱用熱交換器にバイパス配管・弁を設けて、前記浄化装
置の温度を制御することを特徴とする原子炉冷却材浄化
装置。1. A water supply system that deaerates and purifies the water stored in the condenser and supplies it to the reactor with a pump, and the water taken out from the reactor is cooled with a heat exchanger and then purified with a filtration desalination equipment. In a purification device that is heated again in a heat exchanger and returned to the reactor via the water supply device, a bypass piping/valve is provided in the reheat heat exchanger of the purification device to control the temperature of the purification device. A nuclear reactor coolant purification device characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56132718A JPS5834395A (en) | 1981-08-26 | 1981-08-26 | Reactor coolant cleaning device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56132718A JPS5834395A (en) | 1981-08-26 | 1981-08-26 | Reactor coolant cleaning device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5834395A true JPS5834395A (en) | 1983-02-28 |
Family
ID=15087950
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56132718A Pending JPS5834395A (en) | 1981-08-26 | 1981-08-26 | Reactor coolant cleaning device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5834395A (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5666799A (en) * | 1979-11-05 | 1981-06-05 | Hitachi Ltd | Nuclear reactor coolant cleanup system |
-
1981
- 1981-08-26 JP JP56132718A patent/JPS5834395A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5666799A (en) * | 1979-11-05 | 1981-06-05 | Hitachi Ltd | Nuclear reactor coolant cleanup system |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN203394709U (en) | Waste heat conversion system | |
| JPS5834395A (en) | Reactor coolant cleaning device | |
| JPS5912287A (en) | Shellfish-removing device for condenser cooling water | |
| US3095861A (en) | Method and apparatus for extracting heat from the hot exhaust gases of internal combustion engines | |
| CN215489673U (en) | Improvement boiler oxygen-eliminating device temperature of intaking reduces steam of heating transformation system | |
| IL26293A (en) | Method and apparatus for the regulation of the pressure in a primary heat transfer circuit using water under pressure as a heat transfer medium | |
| JPH0440525B2 (en) | ||
| JPS6140763Y2 (en) | ||
| SU1150384A1 (en) | Method of heat supply to consumers | |
| JPS5814909A (en) | Degassing apparatus | |
| RU2078297C1 (en) | Method of heat exchange | |
| JPS604439B2 (en) | How to operate a nuclear reactor plant | |
| JPS59138995A (en) | Condensed water system | |
| JPS5862401A (en) | Steam generator | |
| JPS59155797A (en) | Waste heat recovering and heating system of light water typereactor | |
| RU1815343C (en) | Method of generation of additional power at power-and-heat supply plant with network heaters | |
| JPS58112083A (en) | Heat-accumulating tank | |
| JPH0377402B2 (en) | ||
| JPH0419284Y2 (en) | ||
| SU1084580A1 (en) | Method of adjusting supply line water temperature | |
| JPH05203788A (en) | System for purifying reactor water and fuel pool water | |
| JPS593248Y2 (en) | condensate equipment | |
| JPS5864485A (en) | Condenser | |
| JPH0223929Y2 (en) | ||
| CN109441576A (en) | A kind of saturated vapor electricity generation system |