JPS634677B2 - - Google Patents
Info
- Publication number
- JPS634677B2 JPS634677B2 JP55131623A JP13162380A JPS634677B2 JP S634677 B2 JPS634677 B2 JP S634677B2 JP 55131623 A JP55131623 A JP 55131623A JP 13162380 A JP13162380 A JP 13162380A JP S634677 B2 JPS634677 B2 JP S634677B2
- Authority
- JP
- Japan
- Prior art keywords
- water
- reactor
- water level
- valve
- pool 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.)
- Expired
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 61
- 230000001629 suppression Effects 0.000 claims description 7
- 229920000673 poly(carbodihydridosilane) Polymers 0.000 description 7
- 102100026897 Cystatin-C Human genes 0.000 description 5
- 101000912205 Homo sapiens Cystatin-C Proteins 0.000 description 5
- 238000011109 contamination Methods 0.000 description 4
- 238000002955 isolation Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 2
- 238000005253 cladding Methods 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
- 239000002351 wastewater 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、軽水型原子炉の圧力抑制プール水位
調整法に係り、特に最高水位の調整法に関するも
のである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for adjusting the water level of a pressure suppression pool for a light water nuclear reactor, and particularly to a method for adjusting the maximum water level.
従来の原子炉隔離時冷却系（以下RCICという）
及び高圧炉心スプレイ系（以下HPCSという）の
系統構成を第１図に示す。 Conventional reactor isolation cooling system (hereinafter referred to as RCIC)
Figure 1 shows the system configuration of the high-pressure core spray system (hereinafter referred to as HPCS).
RCICは原子炉１がスクラムし炉１が隔離した
ときに給水が止まり、逃し安全弁から放出される
蒸気により原子炉１の水位が低下するのを防止す
るための系統である。本系統は炉１の水位低信号
によりポンプ２を起動し、復水貯蔵タンク（以下
CSTという）３の水をバルブ４を介し原子炉１
へ補給水を供給する。 The RCIC is a system that prevents the water level in the reactor 1 from dropping due to the steam released from the relief safety valve when the water supply is stopped when the reactor 1 is scrammed and isolated. This system starts pump 2 in response to a low water level signal from reactor 1, and starts pump 2 in the condensate storage tank (hereinafter referred to as
(referred to as CST) 3 to the reactor 1 through valve 4.
Supply water to the area.
また、HPCSはLOCA時に炉心を十分に冷却
し、燃料被覆管の温度を規定値以下に抑えるため
の系統である。本系統は炉１の水位低信号か、ド
ライウエル５の圧力高信号によりポンプ６を起動
し、CST３の水をバルブ４を介し原子炉１へ注
水する。 In addition, the HPCS is a system that sufficiently cools the reactor core during LOCA and keeps the temperature of the fuel cladding below the specified value. In this system, a pump 6 is activated by a low water level signal from the reactor 1 or a high pressure signal from the dry well 5, and water from the CST 3 is injected into the reactor 1 via a valve 4.
更に、HPCSはRCICのバツクアツプ用として
も用いられ、手動によりRCICからHPCSへ切り
換えられる。 Furthermore, HPCS is also used for backing up RCIC, and switching from RCIC to HPCS can be done manually.
しかし、これら両系統は、更に別の信号を検出
すると、サプレツシヨン・プール（以下SPとい
う）７の水を炉１へ注水する。つまり、RCICは
CST３の水位低信号を検出すると、バルブ４を
閉及びバルブ８を開とし、SP７の水を炉１へ注
水する。また、HPCSはSP７の水位高か、CST
３の水位低信号を検出すると、バルブ４を閉及び
バルブ９を開とし、SP７の水を炉１へ注水する。 However, when both of these systems detect another signal, they inject water from the suppression pool (hereinafter referred to as SP) 7 into the reactor 1. In other words, RCIC is
When a low water level signal from CST3 is detected, valve 4 is closed and valve 8 is opened, and water from SP7 is injected into the furnace 1. In addition, HPCS indicates whether the water level is high at SP7 or CST.
When the low water level signal of 3 is detected, the valve 4 is closed and the valve 9 is opened, and water of SP7 is injected into the furnace 1.
以上より、従来次のような炉水汚染の問題があ
つた。つまり、SP７の水位が最高水位（以下
HWLという）に達している場合に、原子炉１が
隔離されると、逃し安全弁を通じてSP７へ蒸気
が放出されるが、残留熱除去系のポンプ１０は蒸
気凝縮モードで運転されているので、ドレン不可
能となり、SP７の水位は上昇し続ける。この結
果、手動によりRCICからHPCSへ切り換えた場
合、CST３の水位が十分でも、SP７の水位高信
号を検出するため、バルブ４を閉、バルブ９と開
とし、SP７の水を炉１へ注水する。このため、
事故でもないのに炉水はSP７の水により汚れて
しまうという炉水汚染の問題があつた。 From the above, conventional reactor water contamination problems have occurred as described below. In other words, the water level of SP7 is the highest water level (hereinafter referred to as
When the reactor 1 is isolated when the reactor 1 reaches the HWL (HWL), steam is released to the SP 7 through the relief safety valve, but since the pump 10 of the residual heat removal system is operated in steam condensation mode, the drain This becomes impossible, and the water level in SP7 continues to rise. As a result, when manually switching from RCIC to HPCS, even if the water level in CST3 is sufficient, in order to detect the high water level signal in SP7, valve 4 is closed, valve 9 is opened, and water from SP7 is injected into furnace 1. . For this reason,
There was a problem of reactor water contamination, in which the reactor water became contaminated with SP7 water even though it was not an accident.
本発明の目的は、原子炉隔離時にSPの水によ
り炉水が汚れるのを防止することにある。 An object of the present invention is to prevent reactor water from being contaminated by SP water during reactor isolation.
本発明は、SPの水位を調整する装置であり、
最高水位を圧力抑制室に通じたドレン機構により
SPの水をSP外へ排出することにより調整する装
置である。 The present invention is a device for adjusting the water level of SP,
A drain mechanism that connects the highest water level to the pressure suppression chamber
This is a device that adjusts the water in the SP by discharging it outside the SP.
本発明の一実施例を図面によつて説明する。 An embodiment of the present invention will be described with reference to the drawings.
本発明の機構は、第２図に示すように、格納容
器１１の圧力抑制室１２内に位置し、圧力抑制室
１２の壁面を貫通した管１３である。管は水面に
開口し、この開口の位置は、SP７のHWLにあ
る。また、このHWLはSP７の最小水量時の最小
プール水深（以下HSWという）に10〜30cmに加
えた値とする。また、格納容器１１の外管の管に
は、LOCA時に格納容器を隔離するためのバルブ
１４を設ける。 As shown in FIG. 2, the mechanism of the present invention is a pipe 13 located within the pressure suppression chamber 12 of the containment vessel 11 and penetrating the wall surface of the pressure suppression chamber 12. The tube opens to the water surface, and the location of this opening is at HWL of SP7. In addition, this HWL is the minimum pool water depth (hereinafter referred to as HSW) at the minimum water flow of SP7 plus 10 to 30 cm. Further, a valve 14 is provided on the outer tube of the containment vessel 11 to isolate the containment vessel during LOCA.
次に、本発明の機能はSP７の水位が上昇して
も、HWLになると水を管１３より排水するとい
うドレン機能を有するものである。SP７の水を
格納容器外へ排水して放射能的には問題ないが、
安全余裕を確保するため、排棄物処理建家へ排水
して処理する。本発明により、次のような効果を
上げることができる。 Next, the function of the present invention is to have a drain function that drains water from the pipe 13 when the water level reaches HWL even if the water level of the SP 7 rises. There is no radioactivity problem by draining SP7 water outside the containment vessel, but
To ensure a safety margin, the waste water will be discharged to a waste treatment building for treatment. According to the present invention, the following effects can be achieved.
(1) 炉水の汚染防止
従来原子炉隔離時に、手動によりRCICから
HPCSへ切り換えた場合、CST３の水位が十分
でも、SP７の水位高信号が検出されると、SP
７の水を炉１へ注水するため、炉１の水が汚れ
た。しかし、本発明により、SP７の最高水位
が調整されるため、CST３の水位低信号を検
出するまで注水されなくなる。このため、一般
的には、原子炉隔離時にはCST３の水位低と
いう事象までは致らないので、炉１の水は汚れ
ないですむ。(1) Preventing reactor water contamination Conventionally, during reactor isolation, water was manually removed from the RCIC.
When switching to HPCS, even if the water level of CST3 is sufficient, if a high water level signal of SP7 is detected, SP
7 was injected into the furnace 1, the water in the furnace 1 became contaminated. However, according to the present invention, since the highest water level of SP7 is adjusted, water will not be injected until the low water level signal of CST3 is detected. For this reason, generally speaking, when the reactor is isolated, the water level of CST3 will not be low, so the water in reactor 1 will not be contaminated.
(2) 稼動率の向上
(1)で示した事象による炉水の汚染防止のた
め、炉水を浄化する期間が解消され、その分の
原子炉の稼動率が向上する。(2) Improved operation rate In order to prevent reactor water contamination due to the events shown in (1), the period for purifying reactor water is eliminated, and the reactor operation rate improves by that amount.
(3) RHRの機能増大
従来のようにRHRのポンプ１０によるSP７
の排水を行う必要がないので、RHRは炉１か
らの蒸気を凝縮して、復水にして再び炉１へ戻
すという本来の機能を逐行できる。(3) Increased functionality of RHR SP7 with RHR pump 10 as before
Since there is no need to drain water, the RHR can carry out its original function of condensing the steam from the furnace 1 and returning it to the furnace 1 as condensate.
第３図及び第４図は、本発明のその他の実施例
第２図と同一部分は同一符号で示す。 In FIGS. 3 and 4, the same parts as in FIG. 2, another embodiment of the present invention, are designated by the same reference numerals.
第３図では、管を水面に対して水平に位置した
もので、管内径の下端部とSP７のHWLとを同一
高さにすることにより、水位調整を行うものであ
る。 In Fig. 3, the pipe is positioned horizontally to the water surface, and the water level is adjusted by making the lower end of the inner diameter of the pipe and the HWL of SP7 the same height.
本発明によれば、原子炉隔離時にSPの水によ
る炉水の汚れを防止でき、稼動率の高い原子炉を
提供することができる。 According to the present invention, it is possible to prevent the reactor water from being contaminated by SP water during reactor isolation, and it is possible to provide a nuclear reactor with a high operating rate.
第１図は従来技術の説明図、第２図は本発明の
一実施例を示す図、第３図は他の実施例を示す図
である。
１……原子炉、２……ポンプ、３……CST、
４……バルブ、５……ドライウエル、６……ポン
プ、７……SP、８……バルブ、９……バルブ、
１０……ポンプ。
FIG. 1 is an explanatory diagram of the prior art, FIG. 2 is a diagram showing one embodiment of the present invention, and FIG. 3 is a diagram showing another embodiment. 1...Reactor, 2...Pump, 3...CST,
4...Valve, 5...Drywell, 6...Pump, 7...SP, 8...Valve, 9...Valve,
10...Pump.
Claims (1)
制室壁面を貫通し、開口部がプール水面に対して
垂直で最高水位位置のプール水面直上の位置で開
口するか、又はその開口部が最高水位位置のプー
ル水面位置で水平上向きで開口し、更に圧力抑制
室外側には弁を有した管で、プール水位を調整す
ることを特徴とする圧力制御プール水位調整装
置。1 In the pressure suppression chamber of a light water reactor, the opening is perpendicular to the pool water surface and opens directly above the pool water surface at the highest water level, or the opening is at the highest water level. A pressure control pool water level adjustment device, characterized in that the pool water level is adjusted by a pipe that opens horizontally upward at the pool water surface position and further has a valve on the outside of the pressure suppression chamber.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55131623A JPS5757290A (en) | 1980-09-24 | 1980-09-24 | Pressure surppression pool water level regulating device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55131623A JPS5757290A (en) | 1980-09-24 | 1980-09-24 | Pressure surppression pool water level regulating device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5757290A JPS5757290A (en) | 1982-04-06 |
| JPS634677B2 true JPS634677B2 (en) | 1988-01-29 |
Family
ID=15062376
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55131623A Granted JPS5757290A (en) | 1980-09-24 | 1980-09-24 | Pressure surppression pool water level regulating device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5757290A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6056642A (en) * | 1983-09-06 | 1985-04-02 | Tachikawa Spring Co Ltd | Seat lifter |
-
1980
- 1980-09-24 JP JP55131623A patent/JPS5757290A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5757290A (en) | 1982-04-06 |
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