JPH0646229B2 - Reactor water level measuring device - Google Patents
Reactor water level measuring deviceInfo
- Publication number
- JPH0646229B2 JPH0646229B2 JP56141106A JP14110681A JPH0646229B2 JP H0646229 B2 JPH0646229 B2 JP H0646229B2 JP 56141106 A JP56141106 A JP 56141106A JP 14110681 A JP14110681 A JP 14110681A JP H0646229 B2 JPH0646229 B2 JP H0646229B2
- Authority
- JP
- Japan
- Prior art keywords
- water level
- reactor
- drum
- pipe
- 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 - Lifetime
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
- Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 本発明は原子炉水位計測装置に係り、特に圧力管型重水
減速炉等に使用する好適な原子炉水位計測装置に関す
る。The present invention relates to a reactor water level measuring device, and more particularly to a reactor water level measuring device suitable for use in a pressure tube type heavy water deceleration reactor or the like.
第1図は従来の圧力管型原子炉の原子炉水位計測装置を
示す系統図である。通常時原子炉1次冷却材(重水)
は、蒸気ドラム1より下降管2及び混合球3を経て、再
循環ポンプ4により昇圧され、逆止弁5、ウオータドラ
ム6及び入口管7を経て原子炉8内の圧力管9に送られ
る。圧力管9内の冷却材は圧力管内に設置されている燃
料集合体10により加熱されて2層流(水と蒸気の混合
流)となつて出口管11を経て蒸気ドラム1に戻り、水
と蒸気に分離される。更に、蒸気は主蒸気管12を経て
タービン系13に送られる。また水はタービン系13か
らの給水管14の給水と混合後再循環される。混合球3
の一部の冷却材は余熱除去系取水配管15により余熱除
去系16に送られ、炉浄化系を経て余熱除去系戻し配管
17によつてウオータドラム6に戻される。なお、余熱
除去系戻し配管17には異常時注水系18が接続されて
いる。FIG. 1 is a system diagram showing a conventional reactor water level measuring device for a pressure tube reactor. Normal reactor primary coolant (heavy water)
Is pressurized from the steam drum 1 via the downcomer pipe 2 and the mixing ball 3 by the recirculation pump 4, and sent to the pressure pipe 9 in the reactor 8 via the check valve 5, the water drum 6 and the inlet pipe 7. The coolant in the pressure pipe 9 is heated by the fuel assembly 10 installed in the pressure pipe to form a two-layer flow (mixed flow of water and steam), returns to the steam drum 1 via the outlet pipe 11, and Separated into steam. Further, the steam is sent to the turbine system 13 via the main steam pipe 12. Further, the water is mixed with the water supply of the water supply pipe 14 from the turbine system 13 and then recirculated. Mixed sphere 3
Part of the coolant is sent to the residual heat removing system 16 through the residual heat removing system intake pipe 15, and is returned to the water drum 6 through the residual heat removing system return pipe 17 through the furnace cleaning system. An abnormal water injection system 18 is connected to the residual heat removal system return pipe 17.
原子炉水位計測装置は蒸気ドラム1の上部(気相部)に
気相部圧力計測用配管19により接続された基準面器2
0、蒸気ドラム1の下部に蒸気ドラム水位計測用配管1
2により接続された蒸気ドラム水位計22及び混合球3
に原子炉水位計測用配管23により接続された原子炉水
位計24から構成されており、これら基準面器20、蒸
気ドラム水位計22、原子炉水位計24の相互間は基準
配管25により接続されている。しかしこのような構成
の従来の原子炉水位計24は、下降管2部の水位を計つ
て間接的に原子炉8の水位を想定しているため、計測精
度が低いという欠点がある。The reactor water level measuring device is a reference level device 2 connected to an upper part (vapor phase part) of a steam drum 1 by a gas phase pressure measuring pipe 19.
0, steam drum water level measurement pipe 1 at the bottom of the steam drum 1
Steam drum water gauge 22 and mixing sphere 3 connected by 2
Is composed of a reactor water level gauge 24 connected by a reactor water level measuring pipe 23 to each other, and a reference pipe 25 is connected between the reference leveler 20, the steam drum water level gauge 22 and the reactor water level gauge 24. ing. However, the conventional reactor water level gauge 24 having such a configuration indirectly measures the water level of the reactor 8 by measuring the water level of the downcomer pipe 2, and thus has a drawback of low measurement accuracy.
即ち、原子炉水位計測が必要となる所内電源喪失時及び
冷却材喪失事故時においては、スクラム後異常時注水系
18によつて余熱除去系戻し配管17を経てウオータド
ラム6に冷却材が注入される。この注入された冷却材は
逆止弁5により混合球3及び下降管2の方へは流れず圧
力管9内へ流れる。従つて実際の原子炉水位は十分ある
にも拘らず、下降管水位を原子炉水位としている上記従
来の原子炉水位計24では、真の原子炉水位を検出でき
ない場合がある。That is, at the time of loss of power source in the station that requires measurement of reactor water level and accident of loss of coolant, coolant is injected into the water drum 6 via the residual heat removal system return pipe 17 by the water injection system 18 at the time of abnormal after scrum. It Due to the check valve 5, the injected coolant does not flow toward the mixing ball 3 and the downcomer pipe 2 but flows into the pressure pipe 9. Therefore, although the actual reactor water level is sufficient, the conventional reactor water level gauge 24, which uses the downcomer pipe water level as the reactor water level, may not be able to detect the true reactor water level.
本発明の目的は、直接原子炉水位を計測し得る精度の高
い原子炉水位計測装置を提供するにある。An object of the present invention is to provide a highly accurate reactor water level measuring device capable of directly measuring the reactor water level.
本発明により上記の目的は、ウオータドラムが炉心部よ
り下位に位置していることと、スクラム時再循環ポンプ
を停止させることに着目し、原子炉水位計をウオータド
ラムに接続して測定箇所をウオータドラムに変更するこ
とにより達成される。According to the present invention, the above-mentioned object is focused on that the water drum is located lower than the core part and that the recirculation pump is stopped at the time of scram, and the reactor water level gauge is connected to the water drum to measure the measurement point. It is achieved by changing to a water drum.
以下、本発明の一実施例を図面に従つて説明する。An embodiment of the present invention will be described below with reference to the drawings.
第2図は本発明に係る原子炉水位計の一実施例の系統図
を示したものである。但し第1図と同様あるいは同一構
成部分は同一符号を用いて示してある。FIG. 2 is a system diagram of an embodiment of the reactor water level gauge according to the present invention. However, the same or the same components as in FIG. 1 are indicated by the same reference numerals.
原子炉1次冷却材は上記ドラム1より下降管2及び混合
球を経て再循環ポンプ4により昇圧され、逆止弁5、ウ
オータドラム6及び入口管7を経て原子炉8内の圧力管
9に送られる。この圧力管9内の燃料集合体10により
加熱された冷却材は2層流となつて出口管11を経て蒸
気ドラム1に戻る。ここで水と蒸気に分離されて蒸気は
主蒸気管12を経てタービン系13へ送られる。水は給
水管14からの給水と混合後再循環される。The primary reactor coolant is pressurized by the recirculation pump 4 from the drum 1 via the downcomer pipe 2 and the mixing sphere, passes through the check valve 5, the water drum 6 and the inlet pipe 7, and enters the pressure pipe 9 in the reactor 8. Sent. The coolant heated by the fuel assembly 10 in the pressure pipe 9 forms a two-layer flow and returns to the steam drum 1 via the outlet pipe 11. Here, the steam is separated into water and steam, and the steam is sent to the turbine system 13 through the main steam pipe 12. The water is mixed with the water supply from the water supply pipe 14 and then recirculated.
本実施例の原子炉水位計測装置では、基準面器20が蒸
気ドラム1の上部に接続され、蒸気ドラム水位計22が
蒸気ドラム1の下部に接続されている。ここまでは従来
例と同様であるが、本実施例の特徴は原子炉水位計24
が原子炉水位計測用配管23によりウオータドラム6に
接続されていることにある。In the reactor water level measuring device of the present embodiment, the reference level 20 is connected to the upper part of the steam drum 1, and the steam drum water level gauge 22 is connected to the lower part of the steam drum 1. Up to this point, it is similar to the conventional example, but the feature of this example is that the reactor water level gauge 24
Is connected to the water drum 6 by a reactor water level measuring pipe 23.
次に本実施例の動作について説明する。通常時は蒸気ド
ラム1内に水面があるので、蒸気ドラム水位計22によ
る検出水位を原子炉水位とみなすことが妥当である。Next, the operation of this embodiment will be described. Since there is a water surface in the steam drum 1 at normal times, it is appropriate to regard the water level detected by the steam drum water level gauge 22 as the reactor water level.
蒸気ドラム1の水位が低下する異常時には、原子炉はス
クラムし再循環ポンプ4は停止する。そして水面が下降
管2まで下がつた場合は、蒸気ドラム水位計22では原
子炉の水位を計測することができなくなる。しかし、本
実施例では圧力管9と常に連通しているウオータドラム
6に接続された原子炉水位計24により真の原子炉水位
を直接測定することができる。実際には、この測定圧力
によりウオータドラム6と蒸気ドラム1間の流動圧損に
よる誤差があるが、この場合、異常時注水系18による
流動圧損は約0.02kg/cm2以下(水位換算でフルスケー
ルの1%以下)でありほとんど無視することができる。When the water level of the steam drum 1 drops, the reactor scrams and the recirculation pump 4 stops. When the water level drops to the downcomer pipe 2, the steam drum water level gauge 22 cannot measure the water level of the reactor. However, in this embodiment, the true reactor water level can be directly measured by the reactor water level gauge 24 connected to the water drum 6 which is always in communication with the pressure pipe 9. Actually, there is an error due to the flow pressure loss between the water drum 6 and the steam drum 1 due to this measured pressure, but in this case, the flow pressure loss due to the abnormal water injection system 18 is about 0.02 kg / cm 2 or less (full scale in water level conversion). Is less than 1%) and can be almost ignored.
本実施例によれば、原子炉水位計24を原子炉水位計測
用配管23によりウオータドラム6に接続することによ
り、蒸気ドラム1の水位が低下する異常時の原子炉水位
を直接且つ精度良く測定し得る効果がある。従つて、原
子力プラントの信頼性を高める効果がある。According to the present embodiment, the reactor water level gauge 24 is connected to the water drum 6 by the reactor water level measurement pipe 23, so that the reactor water level can be directly and accurately measured when the water level of the steam drum 1 is lowered. There are possible effects. Therefore, it has the effect of increasing the reliability of the nuclear power plant.
以上の説明から明らかなように本発明によれば、ウオー
タドラムに原子炉水位計を接続することにより、直接原
子炉水位を計測し得る精度の高い原子炉水位計測装置を
提供することができる。As is clear from the above description, according to the present invention, it is possible to provide a highly accurate reactor water level measuring device capable of directly measuring the reactor water level by connecting the reactor water level gauge to the water drum.
第1図は圧力管型原子炉に備えられた従来の原子炉水位
計測装置の系統図、第2図は本発明に係る原子炉水位計
測装置の一実施例を示す系統図である。 1……蒸気ドラム、2……下降管、3……混合球、4…
…再循環ポンプ、5……逆止弁、6……ウオータドラ
ム、8……原子炉、9……圧力管、10……燃料集合
体、12……主蒸気管、13……タービン系、18……
異常時注水系、20……基準面器、21……蒸気ドラム
水位計測用配管、22……蒸気ドラム水位計、23……
原子炉水位計測用配管、24……原子炉水位計。FIG. 1 is a system diagram of a conventional reactor water level measuring device provided in a pressure tube reactor, and FIG. 2 is a system diagram showing an embodiment of a reactor water level measuring device according to the present invention. 1 ... Steam drum, 2 ... Downcomer, 3 ... Mixing ball, 4 ...
... Recirculation pump, 5 ... Check valve, 6 ... Water drum, 8 ... Reactor, 9 ... Pressure pipe, 10 ... Fuel assembly, 12 ... Main steam pipe, 13 ... Turbine system, 18 ……
Abnormality water injection system, 20 …… Standard surface leveler, 21 …… Steam drum water level measurement piping, 22 …… Steam drum water level gauge, 23 ……
Piping for measuring reactor water level, 24 ... Reactor water level gauge.
Claims (1)
圧した後、炉心部より下位に位置したウオータドラムを
通して前記冷却材を原子炉の圧力管内に送る圧力管型原
子炉の原子炉水位計測装置において、再循環ポンプ停止
後に蒸気ドラムとウオータドラム間の差圧から原子炉水
位を計測する原子炉水位計をウオータドラムに配管によ
り接続したことを特徴とする原子炉水位計測装置。1. A reactor water level of a pressure tube type reactor in which a coolant in a steam drum is pressurized by a recirculation pump, and then the coolant is fed into a pressure pipe of a reactor through a water drum located below a core portion. In the measuring device, a reactor water level measuring device is characterized in that a reactor water level gauge for measuring the reactor water level from the pressure difference between the steam drum and the water drum after the recirculation pump is stopped is connected to the water drum by piping.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56141106A JPH0646229B2 (en) | 1981-09-09 | 1981-09-09 | Reactor water level measuring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56141106A JPH0646229B2 (en) | 1981-09-09 | 1981-09-09 | Reactor water level measuring device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5844389A JPS5844389A (en) | 1983-03-15 |
| JPH0646229B2 true JPH0646229B2 (en) | 1994-06-15 |
Family
ID=15284311
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56141106A Expired - Lifetime JPH0646229B2 (en) | 1981-09-09 | 1981-09-09 | Reactor water level measuring device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0646229B2 (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| AT398721B (en) * | 1992-05-19 | 1995-01-25 | Koninkl Philips Electronics Nv | SHAVER WITH AN ADJUSTABLE TOOTH CUTTER |
| JPH0785753B2 (en) * | 1992-06-25 | 1995-09-20 | 九州日立マクセル株式会社 | Electric razor |
| JP5947600B2 (en) * | 2012-04-10 | 2016-07-06 | 日立Geニュークリア・エナジー株式会社 | Differential pressure type water level gauge for nuclear power plant |
-
1981
- 1981-09-09 JP JP56141106A patent/JPH0646229B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5844389A (en) | 1983-03-15 |
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