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JPH0820545B2 - Core flow measurement device - Google Patents
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JPH0820545B2 - Core flow measurement device - Google Patents

Core flow measurement device

Info

Publication number
JPH0820545B2
JPH0820545B2 JP62183641A JP18364187A JPH0820545B2 JP H0820545 B2 JPH0820545 B2 JP H0820545B2 JP 62183641 A JP62183641 A JP 62183641A JP 18364187 A JP18364187 A JP 18364187A JP H0820545 B2 JPH0820545 B2 JP H0820545B2
Authority
JP
Japan
Prior art keywords
pump
pressure
reactor
core
flow rate
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 - Fee Related
Application number
JP62183641A
Other languages
Japanese (ja)
Other versions
JPS6428595A (en
Inventor
真一 福田
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to JP62183641A priority Critical patent/JPH0820545B2/en
Publication of JPS6428595A publication Critical patent/JPS6428595A/en
Publication of JPH0820545B2 publication Critical patent/JPH0820545B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は原子炉内再循環ポンプが備えられた沸騰水型
原子炉の炉心流量を測定する炉心流量測定装置に係り、
特にポンプ吸込側とポンプ吐出側の差圧を測定するとと
もに、ポンプ回転数を検出して炉心流量を求める炉心流
量測定装置に関する。
The present invention relates to a core flow rate measuring device for measuring a core flow rate of a boiling water reactor equipped with an in-reactor recirculation pump,
In particular, the present invention relates to a core flow rate measuring device for measuring a differential pressure between a pump suction side and a pump discharge side and detecting a pump rotation speed to obtain a core flow rate.

(従来の技術) 一般に、改良型沸騰水型原子炉には炉心へ冷却材とし
ての炉水を循環させる原子炉内再循環ポンプが備えられ
る。
(Prior Art) Generally, an improved boiling water reactor is equipped with an in-reactor recirculation pump that circulates reactor water as a coolant to the core.

第6図および第7図は改良型沸騰水型原子炉の一例を
示す断面図である。原子炉圧力容器(以下RPVという)
1内には炉心シュラウド2が一体的に設けられ、この炉
心シュラウド2に炉心支持板3が水平に固定されるとと
もに、炉心支持板3上に図示しない炉心が備えられる。
また、RPV1の側壁4(以下RPV壁という)には原子炉圧
力容器スカート5が一体に設けられる。
6 and 7 are sectional views showing an example of the improved boiling water reactor. Reactor pressure vessel (hereinafter referred to as RPV)
A core shroud 2 is integrally provided in the core shroud 1, a core support plate 3 is horizontally fixed to the core shroud 2, and a core (not shown) is provided on the core support plate 3.
Further, a reactor pressure vessel skirt 5 is integrally provided on the side wall 4 of the RPV 1 (hereinafter referred to as the RPV wall).

原子炉内再循環ポンプ6はRPV1の底部を形成する原子
炉圧力容器下鏡(以下RPV下鏡という)7を貫通して複
数基設けられ、各原子炉内再循環ポンプは炉心シュラウ
ド2とRPV壁4の間のダウンカマ部8から、シュラウド
サポートレグ9の間を通って、下部プレナム10へ炉水を
循環させるインペラ11と、そのインペラ11を回転駆動さ
せるモータ部12とを有する。また、インペラ11の下流側
にはディフューザ13がポンプデック14に固定して設けら
れ、インペラ11から送り込まれる炉水を拡散させて下部
プレナム10へ送り込むようになっている。
A plurality of in-reactor recirculation pumps 6 are provided so as to penetrate through a reactor pressure vessel lower mirror (hereinafter referred to as RPV lower mirror) 7 forming the bottom of the RPV 1. Each in-reactor recirculation pump is provided with a core shroud 2 and an RPV. It has an impeller 11 for circulating the reactor water from the downcomer portion 8 between the walls 4 to the lower plenum 10 through the shroud support leg 9, and a motor portion 12 for rotationally driving the impeller 11. Further, a diffuser 13 is fixedly provided on the pump deck 14 on the downstream side of the impeller 11, and the reactor water fed from the impeller 11 is diffused and fed to the lower plenum 10.

原子炉内再循環ポンプ6が運転されると、ダウンカマ
部8の炉水はインペラ11の回転により生じる吸引力によ
り吸い込まれるとともに、このインペラ11によって押し
出され、さらにディフューザ13によって拡散された後、
シュラウドサポートレグ9の間から下部プレナム10へ送
り込まれる。
When the in-reactor recirculation pump 6 is operated, the reactor water in the downcomer unit 8 is sucked by the suction force generated by the rotation of the impeller 11, is pushed out by the impeller 11, and is further diffused by the diffuser 13.
It is sent to the lower plenum 10 from between the shroud support legs 9.

下部プレナム10へ送り込まれた炉水は炉水支持板3の
間隙から図示しない炉心内へ入り、炉心の熱を吸収して
炉水の一部が蒸気となり、図示しない気水分離器へ案内
される。一方、蒸気化しなかった炉水および気水分離器
により分離された水は、ダウンカマ部8へ戻り、再び原
子炉内再循環ポンプ6によって炉心へ送り込まれる。
The reactor water sent to the lower plenum 10 enters the core (not shown) through the gap between the reactor water support plates 3, absorbs the heat of the core and part of the reactor water becomes steam, and is guided to a steam separator (not shown). It On the other hand, the reactor water that has not been vaporized and the water separated by the steam separator return to the downcomer unit 8 and are sent again to the core by the in-reactor recirculation pump 6.

ところで、炉心へ送り込まれる冷却材としての炉水の
流量すなわち炉心流量は、原子炉出力や燃料燃焼度等と
密接な関係を有し、原子炉出力や燃料燃焼度等を算出す
る基礎となる。そのため、炉心流量測定装置により炉心
流量が測定されている。
By the way, the flow rate of reactor water as a coolant fed to the core, that is, the core flow rate, has a close relationship with the reactor output, the fuel burnup, etc., and is the basis for calculating the reactor output, the fuel burnup, etc. Therefore, the core flow rate is measured by the core flow rate measuring device.

従来は炉心流量測定装置として原子炉内再循環ポンプ
6のポンプ特性を生かしたポンプデック差圧測定系が使
用されている。ポンプデック差圧測定系の原理は次のよ
うになっている。
Conventionally, a pump deck differential pressure measurement system utilizing the pump characteristics of the recirculation pump 6 in the reactor has been used as a core flow rate measuring device. The principle of the pump deck differential pressure measurement system is as follows.

まず、原子炉の実機納入前試験等で予め実機運転状態
の原子炉内再循環ポンプ6のポンプ回転数をパラメータ
にしたポンプデック差圧−ポンプ流量の関係を求める。
ポンプデック差圧はポンプデック14より上流側の水圧と
下流側の水圧の測定値の差である。また、ポンプ回転数
が0の場合、すなわち停止状態のポンプに順流あるいは
逆流が流れ込む場合のポンプデック差圧−順流流量、ポ
ンプデック差圧−逆流流量の関係についても同様に求め
ておく。
First, in a pre-delivery test of an actual reactor or the like, a relationship between a pump deck differential pressure and a pump flow rate is obtained in advance by using the pump rotation speed of the internal reactor recirculation pump 6 as a parameter.
The pump deck differential pressure is the difference between the measured water pressure on the upstream side and the measured water pressure on the downstream side of the pump deck 14. Further, when the pump rotation speed is 0, that is, when the forward flow or the backward flow flows into the pump in the stopped state, the relationship between the pump deck differential pressure-forward flow rate and the pump deck differential pressure-backflow rate is similarly obtained.

そして実際の運転状態において、各ポンプの回転数お
よびポンプデック差圧を測定する。全部の原子炉内再循
環ポンプ6を運転する場合には予め求めておいたポンプ
デック差圧−ポンプ流量の関係から各ポンプのポンプ流
量を求め、その総和から炉心流量を求める。
Then, in the actual operating state, the rotational speed of each pump and the pump deck differential pressure are measured. When all of the in-reactor recirculation pumps 6 are operated, the pump flow rate of each pump is obtained from the previously obtained relationship between the pump deck differential pressure and the pump flow rate, and the core flow rate is obtained from the sum.

複数の原子炉内再循環ポンプ6のうち一部を運転する
場合には、運転中のポンプについては上記と同様にして
各ポンプのポンプ流量を求め、それらのポンプ流量の総
和をまず求める。次に停止中のポンプについて予め求め
た逆流時のポンプデック差圧−逆流流量の関係から逆流
流量を求め、それらの停止中のポンプの逆流流量の総和
を求める。そして、運転中のポンプのポンプ流量の総和
から停止中のポンプの逆流流量を引いて炉心流量を求め
る。また、原子炉内再循環ポンプ6の全部が停止中であ
る場合には、予め求めた順流時のポンプデック差圧−順
流流量の関係から全ポンプの順流流量の総和を求め、こ
の順流流量の総和から炉心流量を求める。
When a part of the plurality of in-reactor recirculation pumps 6 is operated, the pump flow rate of each pump is calculated in the same manner as described above for the operating pumps, and the sum of the pump flow rates is first calculated. Next, the backflow rate is obtained from the relationship between the pump deck differential pressure during backflow and the backflow rate obtained in advance for the stopped pump, and the total backflow rate of the stopped pumps is obtained. Then, the core flow rate is obtained by subtracting the reverse flow rate of the pump that is stopped from the total pump flow rate of the pump that is operating. When all of the in-reactor recirculation pumps 6 are stopped, the sum of the forward flow rates of all the pumps is calculated from the previously determined relationship between the pump deck differential pressure during forward flow and the forward flow rate. Calculate the core flow rate from the sum.

(発明が解決しようとする問題点) 従来のポンプデック差圧測定系においては、ポンプデ
ック差圧を測定するためにポンプデック差圧測定器16が
備えられる。ポンプデック差圧測定器16は、第6図に示
すようにポンプデック14上流側に設けられたポンプ吸込
側圧力孔17からポンプ吸込側導圧管18を介してポンプ吸
込側圧力を検出する一方、ポンプデック14下流側に設け
られたポンプ吐出側圧力孔19からポンプ吐出側導圧管20
を介してポンプ吐出側圧力を検出し、このポンプ吐出側
圧力と上記ポンプ吸込側圧力との差圧を求めるものであ
る。
(Problems to be Solved by the Invention) In a conventional pump deck differential pressure measuring system, a pump deck differential pressure measuring device 16 is provided to measure the pump deck differential pressure. The pump deck differential pressure measuring device 16 detects the pump suction side pressure from the pump suction side pressure hole 17 provided on the upstream side of the pump deck 14 through the pump suction side pressure guiding pipe 18 as shown in FIG. From the pump discharge side pressure hole 19 provided on the downstream side of the pump deck 14 to the pump discharge side pressure guide tube 20.
The pressure on the discharge side of the pump is detected via, and the pressure difference between the pressure on the discharge side of the pump and the pressure on the suction side of the pump is determined.

従来のポンプデック差圧測定器16のポンプ吸込側圧力
孔17は、第8図に示すように、ポンプデック14とディフ
ューザ13の上端との間に位置し、ポンプ吐出側圧力孔19
はポンプデック14とディフューザ13の下端との間に位置
する。また、平面的には第7図に示すようにポンプ吸込
側圧力孔17は、ディフューザ13と炉心シュラウド2との
間に位置し、ポンプ吐出側圧力孔19は炉心シュラウド2
とRPV壁4に囲まれた区域のシュラウドサポートレグ9
の上方に位置する。
The pump suction side pressure hole 17 of the conventional pump deck differential pressure measuring device 16 is located between the pump deck 14 and the upper end of the diffuser 13, as shown in FIG.
Is located between the pump deck 14 and the lower end of the diffuser 13. Further, as shown in FIG. 7 in plan view, the pump suction side pressure hole 17 is located between the diffuser 13 and the core shroud 2, and the pump discharge side pressure hole 19 is the core shroud 2.
And shroud support leg 9 in the area surrounded by RPV wall 4
Located above.

しかしながら、第8図および第9図に示すようにポン
プデック14上部ではポンプインペラ11へ吸い込まれる主
流A以外の二次流れBが発生し、各ポンプの運転状態の
変化で、この二次流れBが微妙に変化する。
However, as shown in FIGS. 8 and 9, a secondary flow B other than the main flow A that is sucked into the pump impeller 11 is generated in the upper part of the pump deck 14, and due to the change in the operating state of each pump, this secondary flow B Changes subtly.

また、第10図および第11図に示すようにポンプデック
14下部ではシュラウドサポートレグ9開口部へ吐出する
主流A以外の二次流れBが発生し、各ポンプの運転状態
の変化で、この二次流れBが微妙に変化する。
Also, as shown in Figs. 10 and 11, the pump deck
A secondary flow B other than the main flow A discharged to the opening of the shroud support leg 9 is generated in the lower portion of the shroud support leg 9, and the secondary flow B is subtly changed due to a change in the operating state of each pump.

このような二次流れBの変化による圧力の微妙な変化
は、ポンプ吸込側圧力孔17およびポンプ吐出側圧力孔19
に検出され、その結果ポンプデック差圧が不安定とな
り、正確なポンプデック差圧を測定することができな
い。
Subtle changes in pressure due to such changes in the secondary flow B are caused by the pump suction side pressure hole 17 and the pump discharge side pressure hole 19.
Is detected, and as a result, the pump deck differential pressure becomes unstable, and an accurate pump deck differential pressure cannot be measured.

一般に、複数台の原子炉内再循環ポンプ6を有する改
良型沸騰水型原子炉では、各ポンプ間で多様な運転モー
ドが考えられる。そのため、各運転モードにおいて様々
に変化する二次流れBにより、ポンプデック差圧を正確
に測定できない場合には、炉心流量を正確に測定するこ
とができず、プラントの運転余裕を正確に把握できない
ばかりか、燃料経済性を劣化させる結果となる。
Generally, in an improved boiling water reactor having a plurality of in-reactor recirculation pumps 6, various operation modes can be considered between the pumps. Therefore, when the pump deck differential pressure cannot be accurately measured due to the secondary flow B that varies in each operation mode, the core flow rate cannot be accurately measured, and the operating margin of the plant cannot be accurately grasped. Not only that, it will result in a deterioration in fuel economy.

本発明は上記の事情を考慮してなされたもので、複数
の原子炉内再循環ポンプの各運転モードにおける二次流
れの影響を受けることなく、正確なポンプデック差圧を
求めることにより、炉心流量測定精度を向上させること
ができる炉心流量測定装置を提供することを目的とす
る。
The present invention has been made in consideration of the above circumstances, and by obtaining an accurate pump deck differential pressure without being affected by the secondary flow in each operation mode of a plurality of in-reactor recirculation pumps, the core An object of the present invention is to provide a core flow rate measuring device capable of improving flow rate measurement accuracy.

〔発明の構成〕[Structure of Invention]

(問題点を解決するための手段) 本発明は、原子炉内再循環ポンプが備えられた原子炉
におけるポンプ吸込側の圧力とポンプ吐出側の圧力の差
圧を測定するとともに、ポンプ回転数を検出して炉心流
量を求める炉心流量測定装置において、ポンプ吸込側の
圧力検出端をポンプデックから1.5m程度以上上流側のダ
ウンカマ部に設ける一方、ポンプ吐出側の圧力検出端を
炉心シュラウド内側の下部プレナム部に設けたものであ
る。
(Means for Solving the Problem) The present invention measures the differential pressure between the pressure on the pump suction side and the pressure on the pump discharge side in a nuclear reactor equipped with an internal reactor recirculation pump, and In the core flow rate measurement device that detects the core flow rate by detecting it, the pressure detection end on the pump suction side is installed in the downcomer part at about 1.5 m or more upstream from the pump deck, while the pressure detection end on the pump discharge side is located inside the core shroud. It is provided in the plenum.

(作用) 原子炉内再循環ポンプが運転され、ポンプ近傍に二次
流れが発生しても、その二次流れによる吸込側圧力の変
動はポンプデックから1.5m程度以上上流側に設けられた
ポンプ吸込側の圧力検出端には検出されない。
(Operation) Even if the recirculation pump in the nuclear reactor is operated and a secondary flow occurs near the pump, the fluctuation of the suction side pressure due to the secondary flow is a pump provided at least 1.5 m upstream from the pump deck. It is not detected at the pressure detection end on the suction side.

また、二次流れによるポンプ吐出側の圧力の変動は、
炉心シュラウド内側の下部プレナム部にまで及ばないか
ら、ポンプ吐出側の圧力検出端には二次流れによる圧力
の変動の影響がない。
Also, the fluctuation of the pressure on the pump discharge side due to the secondary flow is
Since it does not reach the lower plenum inside the core shroud, the pressure detection end on the pump discharge side is not affected by the pressure fluctuation due to the secondary flow.

したがって、複数の原子炉内再循環ポンプの多様な運
転モードにおいても、二次流れの影響を受けることなく
正確なポンプデック差圧を求めることができ、炉心流量
の測定精度を向上させることができる。
Therefore, even in various operation modes of a plurality of in-reactor recirculation pumps, an accurate pump deck differential pressure can be obtained without being affected by the secondary flow, and the accuracy of core flow rate measurement can be improved. .

(実施例) 本発明に係る炉心流量測定装置の一実施例を図面を参
照して説明する。
(Example) An example of the core flow rate measuring device according to the present invention will be described with reference to the drawings.

第1図および第2図において、原子炉圧力容器(以下
RPVという)1内には炉心シュラウド2が一体的に設け
られ、この炉心シュラウド2に炉心支持板3が水平に固
定されるとともに、炉心支持板3上に図示しない炉心が
備えられる。また、RPV1の側壁4(以下RPV壁という)
には原子炉圧力容器スカート5が一体に設けられる。
1 and 2, the reactor pressure vessel (hereinafter
A core shroud 2 is integrally provided in an RPV (1), a core support plate 3 is horizontally fixed to the core shroud 2, and a core (not shown) is provided on the core support plate 3. In addition, the side wall 4 of RPV1 (hereinafter referred to as RPV wall)
A reactor pressure vessel skirt 5 is provided integrally therewith.

また、RPV1の底部を形成する原子炉圧力容器下鏡(以
下RPV下鏡という)には原子炉内再循環ポンプ6が複数
基設けられ、各原子炉内再循環ポンプ6には炉水を循環
させるインペラ11と、そのインペラ11を回転駆動させる
モータ部12とを有する。
Further, a plurality of reactor pressure vessel lower mirrors (hereinafter referred to as RPV lower mirrors) forming the bottom of the RPV 1 are provided with a plurality of reactor internal recirculation pumps 6, and each reactor internal recirculation pump 6 circulates reactor water. It has an impeller 11 for making it rotate, and a motor unit 12 for driving the impeller 11 to rotate.

上記インペラ11の下流側にはディフューザ13がポンプ
デック14に固定して設けられ、このディフューザ13はイ
ンペラ11から送り込まれる炉水を拡散させて、シュラウ
ドサポートレグ9の間から下部プレナム10へ送り込むよ
うになっている。
A diffuser 13 is fixedly provided on the pump deck 14 on the downstream side of the impeller 11, and the diffuser 13 diffuses the reactor water sent from the impeller 11 and sends it to the lower plenum 10 from between the shroud support legs 9. It has become.

本発明に係る炉心流量測定装置にはポンプデック差圧
測定器16が備えられるとともに、ポンプデック14の上流
側の圧力を検出する圧力検出端としてのポンプ吸込側圧
力孔17と、ポンプデック14の下流側の圧力を検出する圧
力検出端としてのポンプ吐出側圧力孔19とが備えられ
る。
The core flow rate measuring device according to the present invention is provided with a pump deck differential pressure measuring device 16, a pump suction side pressure hole 17 as a pressure detection end for detecting the pressure on the upstream side of the pump deck 14, and the pump deck 14. A pump discharge side pressure hole 19 as a pressure detecting end for detecting the pressure on the downstream side is provided.

上記ポンプデック差圧測定器16は、ポンプ吸込側圧力
孔17で検出されるポンプ吸込側圧力をポンプ吸込側導圧
管18を介して受ける一方、ポンプ吐出側圧力孔19で検出
されるポンプ吐出側圧力をポンプ吐出側導圧管20を介し
て受け、このポンプ吐出側圧力とポンプ吸込側圧力との
差圧をポンプデック差圧として求めるようになってい
る。
The pump deck differential pressure measuring device 16 receives the pump suction side pressure detected by the pump suction side pressure hole 17 via the pump suction side pressure guiding pipe 18, and the pump discharge side detected by the pump discharge side pressure hole 19. The pressure is received via the pump discharge side pressure guiding pipe 20, and the differential pressure between the pump discharge side pressure and the pump suction side pressure is obtained as the pump deck differential pressure.

ところで、原子炉内再循環ポンプ6が運転されること
により、第3図に示すように炉水の主流Aとは別の二次
流れBが発生するが、この二次流れBによるポンプ吸込
側圧力の変動は第4図に示すようにポンプデック14上面
から1.5m程度よりも上方には生じない。
By the way, when the recirculation pump 6 in the reactor is operated, a secondary flow B different from the main flow A of the reactor water is generated as shown in FIG. As shown in FIG. 4, the pressure fluctuation does not occur above 1.5 m from the upper surface of the pump deck 14.

すなわち、第4図の横軸は最大圧力変動を1とした場
合の圧力変動を相対値(無次元圧力変動)として示した
ものであり、縦軸はポンプデック14上面からポンプ上流
側への距離を示したものである。
That is, the horizontal axis in FIG. 4 shows the pressure fluctuation as a relative value (dimensional pressure fluctuation) when the maximum pressure fluctuation is 1, and the vertical axis shows the distance from the upper surface of the pump deck 14 to the upstream side of the pump. Is shown.

このように、ポンプデック14上面から1.5m程度より上
方では二次流れBによる圧力の変動が少ないことから、
本実施例ではポンプ吸込側圧力孔17がポンプデック14上
面から1.5m程度より上方のダウンカマ部の炉心シュラウ
ド2外壁に設けられる。この吸込側圧力孔17はダウンカ
マ部8のRPV壁4に設けてもよい。
As described above, since there is little fluctuation in pressure due to the secondary flow B above about 1.5 m from the upper surface of the pump deck 14,
In the present embodiment, the pump suction side pressure hole 17 is provided in the outer wall of the core shroud 2 in the downcomer portion above the upper surface of the pump deck 14 by about 1.5 m. The suction side pressure hole 17 may be provided in the RPV wall 4 of the downcomer portion 8.

また、インペラ11からディフューザ13に送り込まれた
炉水は、ディフューザ13によって拡散されてから、シュ
ラウドサポートレグ9の間を通って下部プレナム10へ送
り込まれるから、下部プレナム10内の圧力は安定してお
り、二次流れBの影響も及ばない。そのため、本実施例
のポンプ吐出側圧力孔19は下部プレナム10内のシュラウ
ドサポートレグ9上方の炉心シュラウド2内壁に設けら
れる。
Further, the reactor water sent from the impeller 11 to the diffuser 13 is diffused by the diffuser 13 and then sent to the lower plenum 10 through between the shroud support legs 9, so that the pressure in the lower plenum 10 is stable. Therefore, the influence of the secondary flow B is not exerted. Therefore, the pump discharge side pressure hole 19 of this embodiment is provided in the inner wall of the core shroud 2 above the shroud support leg 9 in the lower plenum 10.

一方、平面的な位置関係については第2図に示すよう
に、ポンプ吸込側圧力孔17およびポンプ吐出側圧力孔19
の双方共、各原子炉内再循環ポンプ6の近傍に位置す
る。この実施例では、各原子炉内再循環ポンプ6の間の
ダウンカマ部8をRPV1の中心22から引いた線で4等分
し、それらの区域のうち各原子炉内再循環ポンプ6に近
い区域を越えない範囲に、各圧力孔17,19を設ける。こ
れは、各原子炉内再循環ポンプ6の中間に近い区域は、
双方の原子炉内再循環ポンプ6の運転状態によっては隣
接する原子炉内再循環ポンプ6による圧力変動の影響を
受けることがあるからである。
On the other hand, regarding the planar positional relationship, as shown in FIG. 2, the pump suction side pressure hole 17 and the pump discharge side pressure hole 19 are provided.
Both of them are located in the vicinity of the recirculation pump 6 in each reactor. In this embodiment, the downcomer section 8 between the in-reactor recirculation pumps 6 is divided into four equal parts by a line drawn from the center 22 of the RPV 1, and the areas close to the in-reactor recirculation pumps 6 among these areas. The pressure holes 17 and 19 are provided in a range that does not exceed. This is because the area near the middle of each reactor recirculation pump 6 is
This is because, depending on the operating states of both in-reactor recirculation pumps 6, pressure fluctuations due to the adjacent in-reactor recirculation pumps 6 may be affected.

上記実施例においては、ポンプ吐出側圧力孔19および
ポンプ吸込側圧力孔17を二次流れBによる圧力変動の影
響を受けにくい位置に設けたから、多数の原子炉内再循
環ポンプ6の様々な運転モードにおいても二次流れBの
影響を受けることなく、正確なポンプデック差圧を安定
的に測定して、炉心流量の測定精度を向上させることが
できる。
In the above embodiment, since the pump discharge side pressure hole 19 and the pump suction side pressure hole 17 are provided at positions that are not easily affected by the pressure fluctuations due to the secondary flow B, various operations of the multiple recirculation pumps 6 in the reactor are performed. Even in the mode, the accurate pump deck differential pressure can be stably measured without being affected by the secondary flow B, and the measurement accuracy of the core flow rate can be improved.

炉心流量測定精度の向上は原子炉出力を正確に算出で
きることからプラントの運転性を著しく向上させる他、
燃料経済性の向上にも寄与する。
Improving the accuracy of core flow rate measurement will significantly improve the operability of the plant because the reactor output can be calculated accurately.
It also contributes to the improvement of fuel economy.

第5図は炉心流量測定精度と燃料サイクル費との関係
を示す図である。横軸は定格流量を100%とした場合の
測定誤差を%で表したものであり、縦軸は燃料燃焼度を
100%とした場合の算出誤差を燃料サイクル費の増減と
して%で表したものである。
FIG. 5 is a diagram showing the relationship between the core flow rate measurement accuracy and the fuel cycle cost. The horizontal axis shows the measurement error in% when the rated flow rate is 100%, and the vertical axis shows the fuel burnup.
The calculation error when the value is 100% is expressed in% as the increase / decrease in fuel cycle cost.

すなわち、炉心流量測定精度が悪ければ燃料の燃焼度
を正確に算出することがてきないことから、十分燃料を
燃焼させる前に燃料を交換することになるため燃料サイ
クル費が増加することとなる。一方、炉心流量測定精度
が向上すれば燃料の燃焼度を正確に算出することがで
き、適切な時期に燃料を交換することができるから、燃
料サイクル費を減少させて経済性を向上させることがで
きる。
That is, if the core flow rate measurement accuracy is poor, the burnup of the fuel cannot be calculated accurately, so the fuel must be exchanged before the fuel is sufficiently burned, which increases the fuel cycle cost. On the other hand, if the core flow rate measurement accuracy improves, the burnup of the fuel can be accurately calculated, and the fuel can be replaced at an appropriate time. Therefore, the fuel cycle cost can be reduced and the economic efficiency can be improved. it can.

〔発明の効果〕〔The invention's effect〕

本発明に係る炉心流量測定装置は、ポンプ吸込側圧力
検出端をポンプデックから1.5m程度以上上流側のダウン
カマ部に設ける一方、ポンプ吐出側の圧力検出端を炉心
シュラウド内側の下部プレナム部に設けたから、複数の
原子炉内再循環ポンプの各運転モードにおける二次流れ
の影響を受けることなく、正確なポンプデック差圧を求
めることにより、炉心流量測定精度を向上させることが
できる。したがって、プラントの運転性が向上するとと
もに、燃料の経済性が向上するという効果がある。
In the core flow rate measuring device according to the present invention, the pump suction side pressure detection end is provided in the downcomer portion on the upstream side of about 1.5 m or more from the pump deck, while the pump discharge side pressure detection end is provided in the lower plenum portion inside the core shroud. Therefore, the core flow rate measurement accuracy can be improved by obtaining the accurate pump deck differential pressure without being affected by the secondary flow in each operation mode of the plurality of in-reactor recirculation pumps. Therefore, the operability of the plant is improved and the economical efficiency of the fuel is improved.

【図面の簡単な説明】[Brief description of drawings]

第1図は本発明に係る炉心流量測定装置の一実施例を一
般的な改良型沸騰水型原子炉に組み込んだ状態を示す断
面図、第2図は第1図におけるII−II線矢視図、第3図
は上記実施例におけるポンプデック部分の拡大図、第4
図は圧力変動とポンプデック上面からの距離との関係を
示す図、第5図は炉心流量測定精度と燃料サイクル費の
増減との関係を示す図、第6図は従来の炉心流量測定装
置を一般的な改良型沸騰水型原子炉に組み込んだ状態を
示す断面図、第7図は第6図におけるVII−VII線矢視
図、第8図はポンプデック上流側に生じる二次流れを示
すポンプデック付近の断面図、第9図は第8図における
IX−IX線矢視図、第10図はポンプデック下流側に生じる
二次流れを示すポンプデック付近の断面図、第11図は第
10図におけるXI−XI線矢視図である。 1……原子炉圧力容器、2……炉心シュラウド、4……
原子炉圧力容器壁、6……原子炉内再循環ポンプ、8…
…ダウンカマ部、9……シュラウドサポートレグ、10…
…下部プレナム、11……インペラ、13……ディフュー
ザ、14……ポンプデック、16……ポンプデック差圧測定
器、17……ポンプ吸込側圧力孔、19……ポンプ吐出側圧
力孔。
FIG. 1 is a sectional view showing a state in which an embodiment of the core flow rate measuring device according to the present invention is incorporated in a general improved boiling water reactor, and FIG. 2 is a view taken along the line II-II in FIG. FIGS. 3 and 4 are enlarged views of the pump deck portion in the above embodiment, and FIG.
The figure shows the relationship between the pressure fluctuation and the distance from the upper surface of the pump deck. Fig. 5 shows the relationship between the core flow rate measurement accuracy and the increase / decrease in fuel cycle cost. Fig. 6 shows the conventional core flow rate measuring device. Sectional view showing a state of being incorporated in a general improved boiling water reactor, Fig. 7 is a view taken along the line VII-VII in Fig. 6, and Fig. 8 is a secondary flow occurring on the upstream side of the pump deck. Sectional view near the pump deck, Fig. 9 is in Fig. 8
IX-IX line arrow view, Figure 10 is a sectional view near the pump deck showing the secondary flow occurring on the downstream side of the pump deck, and Figure 11 is the
FIG. 11 is a view taken along the line XI-XI in FIG. 1 ... Reactor pressure vessel, 2 ... Core shroud, 4 ...
Reactor pressure vessel wall, 6 ... Recirculation pump in reactor, 8 ...
... Downcomer part, 9 ... Shroud support leg, 10 ...
… Lower plenum, 11 …… impeller, 13 …… diffuser, 14 …… pump deck, 16 …… pump deck differential pressure measuring instrument, 17 …… pump suction side pressure hole, 19 …… pump discharge side pressure hole.

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】原子炉内再循環ポンプが備えられた原子炉
におけるポンプ吸込側の圧力とポンプ吐出側の圧力の差
圧を測定するとともに、ポンプ回転数を検出して炉心流
量を求める炉心流量測定装置において、ポンプ吸込側の
圧力検出端をポンプデックから1.5m程度以上上流側のダ
ウンカマ部に設ける一方、ポンプ吐出側の圧力検出端を
炉心シュラウド内側の下部プレナム部に設けたことを特
徴とする炉心流量測定装置。
1. A core flow rate for determining a core flow rate by measuring a differential pressure between a pressure on a pump suction side and a pressure on a pump discharge side in a nuclear reactor equipped with an in-reactor recirculation pump In the measuring device, the pressure detection end on the pump suction side is provided in the downcomer part on the upstream side about 1.5 m or more from the pump deck, while the pressure detection end on the pump discharge side is provided in the lower plenum part inside the core shroud. Core flow rate measuring device.
【請求項2】前記ポンプ吸込側の圧力検出端は、各原子
炉内再循環ポンプ上方の炉心シュラウドの外壁または原
子炉圧力容器の内壁に設けられるとともに、前記ポンプ
吐出側の圧力検出端は、各原子炉内再循環ポンプについ
てシュラウドサポートレグ上方の炉心シュラウドの内壁
に設けられた特許請求の範囲第1項記載の炉心流量測定
装置。
2. The pressure detection end on the pump suction side is provided on the outer wall of the core shroud above each in-reactor recirculation pump or the inner wall of the reactor pressure vessel, and the pressure detection end on the pump discharge side comprises: The core flow rate measuring device according to claim 1, which is provided on the inner wall of the core shroud above the shroud support leg for each in-reactor recirculation pump.
JP62183641A 1987-07-24 1987-07-24 Core flow measurement device Expired - Fee Related JPH0820545B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62183641A JPH0820545B2 (en) 1987-07-24 1987-07-24 Core flow measurement device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62183641A JPH0820545B2 (en) 1987-07-24 1987-07-24 Core flow measurement device

Publications (2)

Publication Number Publication Date
JPS6428595A JPS6428595A (en) 1989-01-31
JPH0820545B2 true JPH0820545B2 (en) 1996-03-04

Family

ID=16139341

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62183641A Expired - Fee Related JPH0820545B2 (en) 1987-07-24 1987-07-24 Core flow measurement device

Country Status (1)

Country Link
JP (1) JPH0820545B2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0648309B2 (en) * 1987-10-02 1994-06-22 株式会社日立製作所 Core coolant flow rate measuring device

Also Published As

Publication number Publication date
JPS6428595A (en) 1989-01-31

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