JPH02309295A - Testing method of water pressure of reactor pressure vessel and attached pipings - Google Patents
Testing method of water pressure of reactor pressure vessel and attached pipingsInfo
- Publication number
- JPH02309295A JPH02309295A JP1131118A JP13111889A JPH02309295A JP H02309295 A JPH02309295 A JP H02309295A JP 1131118 A JP1131118 A JP 1131118A JP 13111889 A JP13111889 A JP 13111889A JP H02309295 A JPH02309295 A JP H02309295A
- Authority
- JP
- Japan
- Prior art keywords
- water
- pump
- pressure vessel
- test
- reactor pressure
- 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.)
- Granted
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 142
- 238000012360 testing method Methods 0.000 title claims abstract description 78
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims abstract description 29
- 239000004327 boric acid Substances 0.000 claims abstract description 29
- 238000000746 purification Methods 0.000 claims abstract description 15
- 238000010276 construction Methods 0.000 claims abstract description 12
- 238000010998 test method Methods 0.000 claims description 9
- 238000009835 boiling Methods 0.000 claims description 4
- 238000000034 method Methods 0.000 abstract description 9
- 239000008400 supply water Substances 0.000 abstract 5
- 238000009434 installation Methods 0.000 description 11
- 238000010586 diagram Methods 0.000 description 8
- 230000007246 mechanism Effects 0.000 description 5
- 230000004907 flux Effects 0.000 description 4
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 238000013022 venting Methods 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
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、建設中の沸騰水型原子力発電プラント設置に
おいて、その原子炉圧力容器および付属配管類の水圧試
験方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a method for hydraulic pressure testing of a nuclear reactor pressure vessel and associated piping in the installation of a boiling water nuclear power plant under construction.
（従来の技術）
一般に、建設中の沸騰水型原子力発電プラント設置にお
いては、電気事業法第４１条および第４３条において、
原子炉圧力容器および付属配管類の第一次水圧試験およ
び第二次水圧試験を実施することを義務付けている。(Prior art) Generally, when installing a boiling water nuclear power plant under construction, Articles 41 and 43 of the Electricity Business Act
It is mandatory to conduct primary and secondary hydraulic pressure tests of the reactor pressure vessel and associated piping.
第５図は、従来の原子炉圧力容器および付属配管類の第
一次水圧試験の構成を示すもので、原子炉圧力容器１は
、原子炉格納容器２内に設置され、原子炉圧力容器１に
は付属配管３が接続されている。FIG. 5 shows the configuration of the conventional primary water pressure test of the reactor pressure vessel and attached piping. An attached piping 3 is connected to.
この原子炉圧力容器付属配管３は、第５図では、説明の
便宜上、代表のみを図示しているが、原子炉圧力容器に
付属する配管は、例えば原子炉圧力容器１に接続される
原子炉蒸気配管、給水配管、圧力および水位計等の計装
配管等、多数互いに独立してそれぞれ配設されている。For convenience of explanation, only a representative of the reactor pressure vessel attached piping 3 is shown in FIG. A large number of steam piping, water supply piping, and instrumentation piping such as pressure and water level gauges are installed independently from each other.
原子炉圧力容器１に接続される設置としては、水張接続
があるが、この設置は、復水タンク４、水を張る補給水
ポンプ５および補給水配管６を備え、補給水配管６は、
余熱除去配管７に接続されて原子炉圧力容器１に補給水
を試験水として送水できるようになっている。The installation connected to the reactor pressure vessel 1 is a water-filled connection, and this installation includes a condensate tank 4, a make-up water pump 5 for filling water, and a make-up water pipe 6, and the make-up water pipe 6 is
It is connected to the residual heat removal pipe 7 so that make-up water can be sent to the reactor pressure vessel 1 as test water.
また、試験水を昇温する設置としては、余熱除去ポンプ
８の機械（仕事）エネルギが利用され、原子炉圧力容器
１および再循環ポンプ９の配管から、余熱除去ポンプ８
、余熱除去系熱交換器１１Ｊ。In addition, the mechanical (work) energy of the residual heat removal pump 8 is used to raise the temperature of the test water, and the residual heat removal pump 8 is
, residual heat removal system heat exchanger 11J.
余熱除去配管７および再循環ポンプ出目弁１１の出口配
管を経て原子炉圧力容器１へ戻る流れとなって昇温され
る。The heat flows back to the reactor pressure vessel 1 via the residual heat removal pipe 7 and the outlet pipe of the recirculation pump outlet valve 11, and is heated up.
また、加圧設置としてはほう酸水注入系のほう酸水ポン
プ１゛２およびほう酸水タンク１３が用いられる。ほう
酸水タンク１３内には電気ヒータが配置され、試験水と
して貯留される補給水が加温される。この補給水は、プ
ランジャ式のほう酸水ポンプ１２により、その出口配管
を経て原子炉圧力容器１に供給され、第一次水圧試験に
必要な圧力が、ほう酸水ポンプ１２で加えられる。Further, for pressurizing installation, a boric acid water pump 1-2 and a boric acid water tank 13 of a boric acid water injection system are used. An electric heater is placed in the boric acid water tank 13 to heat makeup water stored as test water. This make-up water is supplied to the reactor pressure vessel 1 via the outlet piping by a plunger-type boric acid water pump 12, and the pressure necessary for the first water pressure test is applied by the boric acid water pump 12.
なお、原子炉圧力容器１に加圧水をベントする配管とし
て、圧力容器ベント配管１４が設置され、またベント水
を受入れる容器として、サンプタンク１５が設置される
。第５図において、符号１６は再循環ポンプ人口弁、符
号１７は逃し安全弁である。Note that a pressure vessel vent pipe 14 is installed as a pipe for venting pressurized water into the reactor pressure vessel 1, and a sump tank 15 is installed as a container for receiving vent water. In FIG. 5, reference numeral 16 is a recirculation pump artificial valve, and reference numeral 17 is a relief safety valve.
第６図は、第一次水圧試験の耐圧範囲を示し、配管に接
続する弁を黒く塗って表わしている。FIG. 6 shows the pressure range of the first water pressure test, and the valves connected to the piping are shown in black.
第７図は、従来の原子炉圧力容器および付属配管類の第
二次水圧試験の構成を示すもので、第５図に示す第一次
水圧試験の構成とほぼ同様である。FIG. 7 shows the configuration of a conventional secondary water pressure test of the reactor pressure vessel and attached piping, which is almost the same as the configuration of the first water pressure test shown in FIG.
すなわち、原子炉圧力容器１に接続される水張り設置は
第５図に示す第一次水圧試験の構成と同一である。That is, the water filling installation connected to the reactor pressure vessel 1 is the same as the configuration of the first water pressure test shown in FIG.
また、試験水を昇温する設置としては、第５図に示す第
一次水圧試験の構成に加え、浄化系ポンプ１８が設置さ
れる。この浄化系ポンプ１８は、原子炉圧力容器１に接
続され、熱交換器１９および浄化設（ｉｉｉ！ ２０を
通り原子炉圧力容器付属配管３に接続されて原子炉圧力
容器］に戻され循環する。In addition to the configuration for the primary water pressure test shown in FIG. 5, a purification system pump 18 is installed to raise the temperature of the test water. This purification system pump 18 is connected to the reactor pressure vessel 1, and is returned to the reactor pressure vessel through a heat exchanger 19 and purification equipment (iii! 20, connected to the reactor pressure vessel attached piping 3, and circulated). .
そして、この浄化系ポンプ１８の機械エネルギを利用し
て昇温を行なう。この設置は、浄化設置２０を有してい
るので、試験水の水質をよくする機能を兼ね備えている
。Then, the mechanical energy of this purification system pump 18 is used to raise the temperature. Since this installation has a purification installation 20, it also has the function of improving the water quality of the test water.
また、加圧設置としては、第７図に示すように、制御棒
駆動水ポンプ２１が設置される。この制御棒駆動水ポン
プ２１の水源は復水タンク４であり、この復水タンク４
内の水は、制御棒駆動ポンプ２１の駆動により、浄化系
の配管に接続したラインより原子炉圧力容器付属配管３
に流れ、原子炉圧力容器１に送られて加圧される。Further, as a pressurizing installation, a control rod driven water pump 21 is installed as shown in FIG. The water source of this control rod driven water pump 21 is a condensate tank 4.
The water inside is pumped through a line connected to the purification system piping to the reactor pressure vessel attached piping 3 by the drive of the control rod drive pump 21.
and is sent to the reactor pressure vessel 1 where it is pressurized.
なお、第５図に示す第一次水圧試験の後、建設進展によ
り設置される設置としては、第７図に示すように、原子
炉圧力容器１下部にそれぞれ設置される制御棒駆動機構
／１ウジング２２および中性子束モニタハウジング２３
があり、制御棒駆動機構ハウジング２２は、制御棒水圧
ユニット２４の出口配管に接続される。制御棒駆動機構
／Ｘウジング２２および中性子束モニタ／Ｘウジング２
３は、第７図では簡略化して示しているが、実際には、
制御棒駆動機構ハウジング２２が１８５本、中性子束モ
ニタハウジング２３が約６０本設置されている。After the first hydraulic test shown in Fig. 5, installations that will be installed as construction progresses include control rod drive mechanisms/1 installed at the bottom of the reactor pressure vessel 1, as shown in Fig. 7. housing 22 and neutron flux monitor housing 23
The control rod drive mechanism housing 22 is connected to the outlet piping of the control rod hydraulic unit 24. Control rod drive mechanism/X-Using 22 and neutron flux monitor/X-Using 2
3 is shown in a simplified manner in Figure 7, but in reality,
There are 185 control rod drive mechanism housings 22 and approximately 60 neutron flux monitor housings 23 installed.
第８図は、第二次水圧試験の耐圧範囲を示し、配管に接
続される弁を黒く塗って表わしている。FIG. 8 shows the pressure range of the second water pressure test, and the valves connected to the pipes are shown in black.
ただし、制御棒水圧ユニット２４は、その水圧ユニット
内の弁が閉となって耐圧バウンダリを構成している。However, the control rod hydraulic unit 24 forms a pressure-resistant boundary with the valves in the hydraulic unit closed.
（発明が解決しようとする課題）
前記従来の原子炉圧力容器および付属配管類の水圧試験
方法においては、第二次水圧試験の実施時期が、建設工
程上、第一次水圧試験より約５ケ月後であること、水圧
試験圧力が、第一次水圧試験では約１１０ｋｇ／ｃｊｇ
、第二次水圧試験では約９０ｋｇ／ｅｊｇと異なってい
ること、耐圧範囲が、第二次水圧試験では、制御棒駆動
機構／Ｘウジング２２、中性子束モニタハウジング２３
、制御棒水圧ユニット２４の出口弁までと広くなってい
ること、および再循環ポンプ９内の部品は、第一次水圧
試験圧力には耐えられないため、第一次水圧試験では、
その出入口弁１１．１６を閉にして実施しなければなら
ないこと等の理由により、第一次水圧試験と第二次水圧
試験とを別々に行なう方法を採っている。このため、建
設工程が長くなるとともに、同じような複雑な操作を２
回も実施しなければならないため、コスト高となるとい
う問題がある。(Problems to be Solved by the Invention) In the conventional water pressure test method for reactor pressure vessels and attached piping, the timing of the second water pressure test is approximately five months after the first water pressure test due to the construction process. The water pressure test pressure was approximately 110kg/cjg in the first water pressure test.
In the second water pressure test, the pressure range was different from about 90 kg/ejg, and in the second water pressure test, the control rod drive mechanism/X housing 22, neutron flux monitor housing 23
In the first hydraulic test, the control rods are wide enough to reach the outlet valve of the hydraulic unit 24, and the parts inside the recirculation pump 9 cannot withstand the first hydraulic test pressure.
For reasons such as the fact that the inlet/outlet valves 11 and 16 must be closed, a method is adopted in which the primary water pressure test and the secondary water pressure test are conducted separately. This lengthens the construction process and requires the same complex operations to be performed twice.
There is a problem in that the cost is high because it has to be carried out multiple times.
本発明は、このような点を考慮してなされたもので、第
一次水圧試験と第二次水圧試験とを同時期に行なって、
建設工事の工程を短縮することができる原子炉圧力容器
および付属配管類の水圧試験方法を提供することを目的
とする。The present invention was made in consideration of these points, and the first water pressure test and the second water pressure test were conducted at the same time.
The purpose of this invention is to provide a method for hydraulic pressure testing of nuclear reactor pressure vessels and associated piping, which can shorten the construction process.
（課題を解決するための手段）
本発明は、前記目的を達成する手段として、建設中の沸
騰水型原子力発電プラント設置の原子炉圧力容器および
付属配管類の水圧試験方法において、復水タンクに貯留
されている補給水を、付属配管類を介して原子炉圧力容
器に供給し、次いで再循環ポンプ、余熱除去ポンプおよ
び浄化系ポンプを駆動し、その機械エネルギで補給水を
規定温度まで昇温して前記各ポンプを停止し、次いでほ
う酸水タンク内で加温された補給水を、ほう酸水ポンプ
により原子炉圧力容器に供給して第二次水圧試験を行な
い、次いで再循環ポンプを隔離するとともに、制御棒駆
動水ポンプを駆動し補給水を原子炉圧力容器に供給して
第一次水圧試験を行なうようにしたことを特徴とする。(Means for Solving the Problems) As a means for achieving the above object, the present invention provides a water pressure test method for a reactor pressure vessel and attached piping installed in a boiling water nuclear power plant under construction. The stored makeup water is supplied to the reactor pressure vessel via attached piping, and then the recirculation pump, residual heat removal pump, and purification system pump are driven, and the mechanical energy is used to raise the temperature of the makeup water to a specified temperature. Then, the make-up water heated in the boric acid water tank is supplied to the reactor pressure vessel by the boric acid water pump to conduct a second hydraulic pressure test, and then the recirculation pump is isolated. In addition, the control rod-driven water pump is driven to supply make-up water to the reactor pressure vessel to conduct the primary water pressure test.
（作 用）
この発明に係る原子炉圧力容器および付属配管類の水圧
試験方法においては、復水タンク内の補給水が、原子炉
圧力容器に満水になる程度に供給され、この補給水は、
再循環ポンプ等の駆動により、その機械エネルギで所定
の試験温度まで加熱されて各ポンプが停止される。そし
て、ほう酸水タンク内で加温された補給水が、原子炉圧
力容器に供給されて第二次水圧試験が行なわれる。次い
で、再循環ポンプが隔離されるとともに、制御棒駆動水
ボンブカｉ駆動されて原子炉圧力容器がさらに加圧され
、第一次水圧試験が実施される。すなわち、低圧の第二
次水圧試験が行なわれた後、引き続き高圧の第一次水圧
試験が行なわれる。(Function) In the water pressure testing method for a reactor pressure vessel and attached piping according to the present invention, make-up water in the condensate tank is supplied to the extent that the reactor pressure vessel is filled with water, and this make-up water is
When a recirculation pump or the like is driven, the mechanical energy is used to heat the pump to a predetermined test temperature, and then each pump is stopped. The make-up water heated in the boric acid water tank is then supplied to the reactor pressure vessel and a second hydraulic pressure test is conducted. Next, the recirculation pump is isolated, and the control rod-driven water bomber is driven to further pressurize the reactor pressure vessel, and the first hydraulic pressure test is performed. That is, after the low-pressure secondary water pressure test is conducted, the high-pressure primary water pressure test is subsequently conducted.
（実施例）
以下、本発明の実施例について図面を参照して説明する
。(Example) Hereinafter, an example of the present invention will be described with reference to the drawings.
第１図は、本発明に係る原子炉圧力容器および付属配管
類の水圧試験方法の一例を示すもので、第一次水圧試験
および第二次水圧試験の双方を組合せた構成を示す。な
お、第１図中、第５図ないし第８図と同一部分は同一符
号を示し、１護を避けるため、その詳細な説明は省略す
る。FIG. 1 shows an example of a water pressure test method for a reactor pressure vessel and attached piping according to the present invention, and shows a configuration in which both a primary water pressure test and a secondary water pressure test are combined. Note that in FIG. 1, the same parts as in FIGS. 5 to 8 are denoted by the same reference numerals, and detailed explanations thereof will be omitted to avoid numerals.
第１図において、前記第７図の構成に追加されている設
置は、加圧設置としてのほう酸水注入系のほう酸水ポン
プ１２およびほう酸水タンク１３である。In FIG. 1, installations added to the configuration of FIG. 7 are a boric acid water pump 12 and a boric acid water tank 13 of a boric acid water injection system as pressurized installations.
ポンプ１２で供給配管を介して原子炉圧力容器に供給さ
れ、原子炉水圧試験に必要な圧力をほう酸水ポンプ１２
で加えられるようになっている。またほう酸水タンク１
３の補給水は、ほう酸水タンク１３に内蔵した電気ヒー
タで加温されるようになっている。Boric acid water is supplied to the reactor pressure vessel via the supply pipe by the pump 12, and the pressure necessary for the reactor water pressure test is supplied to the boric acid water pump 12.
It can be added with . Also, boric acid water tank 1
The make-up water No. 3 is heated by an electric heater built into the boric acid water tank 13.
第２図は、第一次水圧試験および第二次水圧試験を同時
に実施する際の原子炉水圧試験バウンダリ構成を示すも
ので、配管に接続される弁を黒く塗って表わしている。Figure 2 shows the reactor water pressure test boundary configuration when the primary water pressure test and the secondary water pressure test are conducted simultaneously, and the valves connected to the piping are shown in black.
なお、制御棒水圧ユニット２４は、その水圧ユニット内
の弁を閉としてバウンダリ構成となっている。Note that the control rod hydraulic unit 24 has a boundary configuration with the valve within the hydraulic unit closed.
次に、第３図を参照して、第一次水圧試験および第二次
水圧試験を同時に実施する水圧試験方法について説明す
る。Next, with reference to FIG. 3, a water pressure test method in which a first water pressure test and a second water pressure test are conducted simultaneously will be described.
復水タンク４に貯留されている補給水は、補給水ポンプ
５の駆動により、補給水配管６および余熱除去配管７を
介し原子炉圧力容器１に満水になる程度までＯ（給され
る。The make-up water stored in the condensate tank 4 is supplied with O (O) through the make-up water pipe 6 and the residual heat removal pipe 7 to the extent that the reactor pressure vessel 1 is filled with water by driving the make-up water pump 5.
原子炉圧力容器１に補給された水は原子炉圧力容器１に
接続される配管を通り、後述する各ポンプに入り循環す
る。そして、各ポンプを運転して循環させることにより
、ポンプの機械エネルギを利用して補給水の昇温かなさ
れる。Water supplied to the reactor pressure vessel 1 passes through piping connected to the reactor pressure vessel 1, enters each pump described later, and circulates. By operating and circulating each pump, the temperature of the make-up water is raised using the mechanical energy of the pumps.
なお、機械エネルギで補給水の温度を規定試験温度（約
４０℃）まで上昇させるポンプは、再循環ポンプ９、余
熱除去ポンプ８および浄化系ポンプ１８の３種類のポン
プである。There are three types of pumps that raise the temperature of makeup water to the specified test temperature (approximately 40° C.) using mechanical energy: the recirculation pump 9, the residual heat removal pump 8, and the purification system pump 18.
補給水が規定試験温度まで上昇すると、原子炉圧力容器
１に加圧する準備として、各ポンプ８゜９．１８を停止
トシ、浄化系止め弁２５、余熱除去系吸込側止め弁２６
および余熱除去系吐出側止め弁２７を閉にする。When the make-up water rises to the specified test temperature, in preparation for pressurizing the reactor pressure vessel 1, each pump 8゜9.18 is stopped, the purification system stop valve 25, and the residual heat removal system suction side stop valve 26.
And the residual heat removal system discharge side stop valve 27 is closed.
この状態で、ほう酸水タンク１３内で温められた補給水
を、ほう酸水ポンプ１２から配管を介して原子炉圧力容
器１に供給し、原子炉圧力容器１を補給水で満水にする
。原子炉圧力容器１の上部に溜っている空気は、圧力容
器ベント配管１４を介しサンプタンク１５に排出する。In this state, make-up water warmed in the boric acid water tank 13 is supplied from the boric acid water pump 12 to the reactor pressure vessel 1 via piping to fill the reactor pressure vessel 1 with make-up water. Air accumulated in the upper part of the reactor pressure vessel 1 is discharged to the sump tank 15 via the pressure vessel vent pipe 14.
この排出作業後、ベント弁２８および浄化系ポンプ吐出
弁２９を閉にし、第二次水圧試験と同ｔａｐの試験圧力
（約９０ ｋｇ／ｃｄ ｇ ）になるまでほう酸水ポン
プ１２を運転する。After this discharge work, the vent valve 28 and the purification system pump discharge valve 29 are closed, and the boric acid water pump 12 is operated until the test pressure reaches the same tap as the second water pressure test (approximately 90 kg/cd g).
試験圧力になると、ほう酸水ポンプ１２を停止し、接続
配管止め弁３０およびほう酸水ポンプ山口弁３１を閉に
する。When the test pressure is reached, the boric acid water pump 12 is stopped, and the connecting piping stop valve 30 and the boric acid water pump Yamaguchi valve 31 are closed.
これにより、原子炉圧力容器１および付属配管類の第二
次水圧試験と同様な試験が可能となる。This makes it possible to perform a test similar to the second water pressure test of the reactor pressure vessel 1 and attached piping.
第４図は、その際の耐圧試験範囲を示し、配管に接続さ
れる弁を黒く塗って表わしている。なお、制御棒水圧ユ
ニット２４は、その水圧ユニット内の弁を閉としてバウ
ンダリ構成としている。FIG. 4 shows the pressure resistance test range at that time, and the valves connected to the pipes are shown in black. Note that the control rod hydraulic unit 24 has a boundary configuration with the valve within the hydraulic unit closed.
このようにして、約９０ｋｇ／ｃｄｇまでの水圧試験が
終了したならば、再循環ポンプ９の出口弁１１および入
口弁１６を閉じ、次の試験からＦＩＧ循環ポンプ９を隔
離する。In this way, once the water pressure test to about 90 kg/cdg has been completed, the outlet valve 11 and inlet valve 16 of the recirculation pump 9 are closed to isolate the FIG circulation pump 9 from the next test.
次いで、耐圧バウンダリを一部解除するため、接続配管
止め弁３０および浄化系ポンプ出口弁２９を開にし、浄
化系止め弁２５を閉にする。そして、この状態で加圧を
行なう。Next, in order to partially release the pressure boundary, the connection piping stop valve 30 and the purification system pump outlet valve 29 are opened, and the purification system stop valve 25 is closed. Then, pressurization is performed in this state.
この加圧は、制御棒駆動水ポンプ２１を運転し、復水タ
ンク４に貯留されている補給水を、制御棒駆動水止め弁
３２および接続配管止め弁３０を介し原子炉圧力容器１
に送ることにより行なイ）れる。This pressurization operates the control rod drive water pump 21 to supply makeup water stored in the condensate tank 4 to the reactor pressure vessel through the control rod drive water stop valve 32 and the connection piping stop valve 30.
a) by sending it to
制御棒駆動水ポンプ２１は、規定の試験圧力（約１１０
ｋｇ／ｃｊｇ）になるまで運転される。The control rod-driven water pump 21 is operated at a specified test pressure (approximately 110
kg/cjg).
試験圧力になると、制御棒駆動水ポンプ２１を停止し、
接続配管止め弁３０を閉にする。そして、この状態で水
圧試験を行なう。When the test pressure is reached, the control rod driven water pump 21 is stopped,
Close the connecting pipe stop valve 30. Then, in this state, a water pressure test is conducted.
このようにして約９０ｋｇ／ｃｄｇでの第二次水圧試験
と、約１１０ ｋｇ／ｃｄ ｇでの第一次水圧試験とを
、連続して行なうことが可能となる。In this way, it is possible to carry out the secondary water pressure test at about 90 kg/cdg and the first water pressure test at about 110 kg/cdg in succession.
以上説明したように本発明は、わざわざ２回に分離せず
、１回目の水圧試験の実施をわずかにずらして、第一次
水圧試験と第二次水圧試験とを同時に実施するようにし
ているので、建設コストを低減させることができる。ま
た、水圧試験を１回分削減したことにより、建設工事の
工程を短縮することができる。As explained above, in the present invention, the first water pressure test is carried out at the same time as the first water pressure test and the second water pressure test is carried out at the same time, without going through the trouble of separating the tests into two. Therefore, construction costs can be reduced. Furthermore, by reducing the number of hydraulic tests by one, the construction process can be shortened.
第１図は本発明実施の一例に係る原子炉圧力容器および
付属配管類の水圧試験方法を示す構成図、第２図はその
際のバウンダリ構成図、第３図は水圧試験時の構成図、
第４図はその際の耐圧試験範囲を示す説明図、第５図は
従来の原子炉圧力容器および付属配管類の水圧試験方法
における第一次水圧試験時の構成図、第６図はその際の
耐圧範囲を示す説明図、第７図は従来の水圧試験方法に
おける第二次水圧試験時の構成図、第８図はその際の耐
圧範囲を示す説明図である。
１・・・原子炉圧力容器、３・・・原子炉圧力容器付属
配管、４・・・復水タンク、５・・・補給水ポンプ、８
・・・余熱除去ポンプ、９・・・再循環ポンプ、１１・
・・再循環ポンプ出目弁、１２・・・ほう酸水ポンプ、
１３・・・ほう酸水タンク、１６・・・再循環ポンプ人
口弁、１８・・・浄化系ポンプ、２１・・・制御棒駆動
水ポンプ。
出願人代理人 佐 藤 −雄
ｉ／’、ＩＩＢ
第 ２［ｉｉａ
第 ３ 図
第 ４ 図
第 ５ 図
第 σ 図
第 ７ 図Fig. 1 is a block diagram showing a hydraulic pressure test method for a reactor pressure vessel and attached piping according to an example of implementing the present invention, Fig. 2 is a boundary block diagram at that time, and Fig. 3 is a block diagram during a water pressure test.
Figure 4 is an explanatory diagram showing the pressure test range at that time, Figure 5 is a configuration diagram at the time of the first water pressure test in the conventional water pressure test method for the reactor pressure vessel and attached piping, and Figure 6 is the diagram at the time. FIG. 7 is an explanatory diagram showing the pressure range at the time of the second water pressure test in the conventional water pressure test method, and FIG. 8 is an explanatory diagram showing the pressure range at that time. 1... Reactor pressure vessel, 3... Reactor pressure vessel attached piping, 4... Condensate tank, 5... Make-up water pump, 8
... Residual heat removal pump, 9... Recirculation pump, 11.
... Recirculation pump outlet valve, 12... Boric acid water pump,
13... Boric acid water tank, 16... Recirculation pump artificial valve, 18... Purification system pump, 21... Control rod driven water pump. Applicant's agent: Sato-Yu I/', IIB No. 2 [IIA Fig. 3 Fig. 4 Fig. 5 Fig. σ Fig. 7
Claims (1)
容器および付属配管類の水圧試験方法において、復水タ
ンクに貯留されている補給水を、付属配管類を介して原
子炉圧力容器に供給し、次いで再循環ポンプ、余熱除去
ポンプおよび浄化系ポンプを駆動し、その機械エネルギ
で補給水を規定温度まで昇温して前記各ポンプを停止し
、次いでほう酸水タンク内で加温された補給水を、ほう
酸水ポンプにより原子炉圧力容器に供給して第二次水圧
試験を行ない、次いで再循環ポンプを隔離するとともに
、制御棒駆動水ポンプを駆動し補給水を原子炉圧力容器
に供給して第一次水圧試験を行なうことを特徴とする原
子炉圧力容器および付属配管類の水圧試験方法。In the water pressure test method for the reactor pressure vessel and attached piping in a boiling water nuclear power plant under construction, make-up water stored in the condensate tank is supplied to the reactor pressure vessel via the attached piping. Then, the recirculation pump, residual heat removal pump, and purification system pump are driven, and the mechanical energy is used to raise the temperature of the make-up water to the specified temperature and stop each pump, and then the make-up water heated in the boric acid water tank is heated. A second water pressure test was carried out by supplying water to the reactor pressure vessel using a boric acid water pump, and then the recirculation pump was isolated and the control rod drive water pump was driven to supply make-up water to the reactor pressure vessel. A water pressure test method for a reactor pressure vessel and attached piping, characterized by conducting a primary water pressure test.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1131118A JP2675622B2 (en) | 1989-05-24 | 1989-05-24 | Water pressure test method for reactor pressure vessel and attached piping |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1131118A JP2675622B2 (en) | 1989-05-24 | 1989-05-24 | Water pressure test method for reactor pressure vessel and attached piping |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02309295A true JPH02309295A (en) | 1990-12-25 |
| JP2675622B2 JP2675622B2 (en) | 1997-11-12 |
Family
ID=15050408
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1131118A Expired - Lifetime JP2675622B2 (en) | 1989-05-24 | 1989-05-24 | Water pressure test method for reactor pressure vessel and attached piping |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2675622B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102568629A (en) * | 2012-02-02 | 2012-07-11 | 中广核工程有限公司 | Power supply method for nuclear power plant cold-state function test |
| CN110748473A (en) * | 2019-10-14 | 2020-02-04 | 武汉瑞莱保能源技术有限公司 | Intelligent pressure regulating system and method for loop pressure test hydrostatic test pump |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107437436B (en) * | 2017-07-28 | 2019-02-22 | 中国核动力研究设计院 | It is able to carry out the secondary circuit energy consumption simulation test device and method of power regulation |
-
1989
- 1989-05-24 JP JP1131118A patent/JP2675622B2/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102568629A (en) * | 2012-02-02 | 2012-07-11 | 中广核工程有限公司 | Power supply method for nuclear power plant cold-state function test |
| CN110748473A (en) * | 2019-10-14 | 2020-02-04 | 武汉瑞莱保能源技术有限公司 | Intelligent pressure regulating system and method for loop pressure test hydrostatic test pump |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2675622B2 (en) | 1997-11-12 |
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