JPS62198792A - Pressure resistance testing method of nuclear reactor pressure vessel and attendant piping - Google Patents
Pressure resistance testing method of nuclear reactor pressure vessel and attendant pipingInfo
- Publication number
- JPS62198792A JPS62198792A JP61042315A JP4231586A JPS62198792A JP S62198792 A JPS62198792 A JP S62198792A JP 61042315 A JP61042315 A JP 61042315A JP 4231586 A JP4231586 A JP 4231586A JP S62198792 A JPS62198792 A JP S62198792A
- Authority
- JP
- Japan
- Prior art keywords
- water
- reactor
- pressure vessel
- reactor pressure
- pump
- 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
- 238000012360 testing method Methods 0.000 title claims description 15
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 60
- 238000010438 heat treatment Methods 0.000 claims description 18
- 238000002347 injection Methods 0.000 claims description 13
- 239000007924 injection Substances 0.000 claims description 13
- 239000008400 supply water Substances 0.000 claims description 10
- 238000010998 test method Methods 0.000 claims description 9
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims 1
- 239000004327 boric acid Substances 0.000 claims 1
- 239000000498 cooling water Substances 0.000 description 14
- 239000007921 spray Substances 0.000 description 5
- 238000009434 installation Methods 0.000 description 4
- 238000010276 construction Methods 0.000 description 3
- 238000002156 mixing Methods 0.000 description 3
- 239000002023 wood Substances 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000002955 isolation Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 238000000034 method 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (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】
「産業上の利用分野」
本発明は原子炉圧力容器及び付属配管の耐圧試験方法に
関するものである。DETAILED DESCRIPTION OF THE INVENTION "Field of Industrial Application" The present invention relates to a pressure test method for a nuclear reactor pressure vessel and associated piping.
「従来の技術とその問題点」
原子炉圧力容器の付属配管は、原子炉の運転開始前等に
所要の耐圧試験を実施して、その健全性を確認するよう
にしている。``Prior Art and Its Problems'' The pipes attached to the reactor pressure vessel are subjected to the necessary pressure tests to confirm their integrity before the reactor starts operating.
沸騰水型原子炉における原子炉圧力容器及び付属配管の
耐圧試験方法の従来例について、第２図に基づいて説明
すると、原子炉圧力容器１の中に給水手段２によって水
（純水）を充満するとともに、その給水の途中で加熱手
段３により試験適温まで加熱した後、加圧手段４を作動
させて、試験圧力、例えば水圧１１５ｋｇ／ｃｍ”まで
高めて耐圧試験を実施するものであり、そして、第２図
に鎖線で示すこれらの手段、つまり給水手段２と加熱手
段３と加圧手段４とは、それぞれ沸騰水型原子カプラン
ト本来の設備に関係なく仮設されるものである。A conventional example of a pressure test method for a reactor pressure vessel and attached piping in a boiling water reactor will be explained based on FIG. 2. A reactor pressure vessel 1 is filled with water (pure water) by a water supply means 2. At the same time, during the water supply, the water is heated to an appropriate test temperature by the heating means 3, and then the pressurizing means 4 is activated to increase the test pressure, for example, the water pressure to 115 kg/cm'', and a pressure resistance test is carried out. These means shown by chain lines in FIG. 2, that is, the water supply means 2, the heating means 3, and the pressurizing means 4, are temporarily installed irrespective of the original equipment of the boiling water type atomic couplant.
また、前記給水手段２は、純水タンク５の純水をポンプ
６により濾過水タンク７に送り込んで濾過した後、濾過
水を矢印で示すように、加熱手段３に送り出すものであ
り、該加熱手段３は、濾過水をミキシングタンク８に貯
留するとともに、その貯留水に蒸気供給系（補助ボイラ
等）９から蒸気を送り込んで試験適温まで加熱し、ポン
プ６の作動により、矢印で示すように、適温水を仮設配
管１０を経由して原子炉格納容器１１の中の原子炉冷却
水再循環系１２に合流させ、該原子炉冷却水再循環系１
２のポンプ吐出側配管を経由して、矢印で示すように原
子炉圧力容器ｌへ送り込む。そして、原子炉圧力容器ｌ
に貯留された水は、再び循環するために、原子炉圧力容
器■の下鏡、原子炉冷却水浄化系１３の配管の一部を経
由して、原子炉圧力容器■の外へ抜き出され、仮設配管
ｌＯにより原子炉格納容器１１の外の前記ミキシングタ
ンク８に戻され、再び加熱、循環させられる。また、加
熱手段３を作動させた場合の戻り水は、原子炉圧力容器
ｌの上鏡から他の仮設配管１４により原子炉格納容器１
１の中の仮設配管ＩＯに合流させることができるとと乙
に、主蒸気配管１５及び原子炉隔離時冷却系１６から引
き出して、仮設配管ＩＯに合流させることらできるよう
にしている。Further, the water supply means 2 is configured to send pure water from a pure water tank 5 to a filtered water tank 7 using a pump 6 to filter it, and then send the filtered water to a heating means 3 as shown by an arrow. Means 3 stores filtered water in a mixing tank 8, feeds steam into the stored water from a steam supply system (auxiliary boiler, etc.) 9, heats it to the appropriate test temperature, and operates the pump 6 to generate water as shown by the arrow. , the appropriate temperature water is joined to the reactor cooling water recirculation system 12 in the reactor containment vessel 11 via the temporary piping 10, and the reactor cooling water recirculation system 1
It is sent to the reactor pressure vessel l via the pump discharge side pipe No. 2 as shown by the arrow. And reactor pressure vessel l
The water stored in the reactor pressure vessel is drawn out of the reactor pressure vessel ■ via the lower mirror of the reactor pressure vessel ■ and a part of the piping of the reactor cooling water purification system 13 in order to be circulated again. , and is returned to the mixing tank 8 outside the reactor containment vessel 11 via a temporary pipe IO, where it is heated and circulated again. In addition, when the heating means 3 is activated, the return water is transferred from the upper mirror of the reactor pressure vessel l to another temporary pipe 14 to the reactor containment vessel 1.
If it is possible to join the temporary piping IO in 1, it is also possible to draw it out from the main steam piping 15 and the reactor isolation cooling system 16 and join it with the temporary piping IO.
さらに、前記加圧手段４を実施する場合は、６弁１７を
閉塞した状態として、加熱手ｙＸ３から吐出された加熱
水を仮設配管１０の途中等から分岐配管１８によりプラ
ンジャポンプ１９に導き、該プランジャポンプ１９によ
り加圧水を発生させて、該加圧水をヘッダ２０、加圧水
供給管２１を経由して原子炉冷却水再循環系１２に送り
、原子炉冷却水再循環系１２のポンプ吸引側配管、原子
炉冷却水再循環用ポンプ２２、ポンプ吐出配管を経由し
て、矢印で示すように原子炉圧力容器ｌへ送り込み、必
要とする圧力まで高めるものである。第２図中、太線の
配管は、耐圧試験の対象部分である。Furthermore, when implementing the pressurizing means 4, the six valves 17 are closed, and the heated water discharged from the heating hand yX3 is guided from the middle of the temporary pipe 10 to the plunger pump 19 through the branch pipe 18. Pressurized water is generated by the plunger pump 19 and sent to the reactor cooling water recirculation system 12 via the header 20 and the pressurized water supply pipe 21, and the pump suction side piping of the reactor cooling water recirculation system 12, the The reactor cooling water is sent via the reactor cooling water recirculation pump 22 and pump discharge piping to the reactor pressure vessel l as shown by the arrow, and the pressure is increased to the required level. In Fig. 2, the thick line piping is the part to be subjected to the pressure resistance test.
なお、耐圧試験終了後において、原子炉圧力容器１の中
の水は、排水配管２３によって抜き取られ、機器ザンブ
タンク２４に落とされて処理される。また符号２５は給
水系、符号２６は高圧炉心スプレ系、符号２７は低圧炉
心スプレ系、符号２８は原子炉残留熱除去系、符号２９
はほう成木注入系を表している。Note that after the pressure test is completed, the water in the reactor pressure vessel 1 is drained out through the drainage pipe 23 and dropped into the equipment tank 24 for treatment. Further, numeral 25 is a water supply system, numeral 26 is a high pressure core spray system, numeral 27 is a low pressure core spray system, numeral 28 is a reactor residual heat removal system, and numeral 29 is
represents a mature tree injection system.
しかしながら、このような試験方法であると、原子炉の
構築作業と平行して、仮設設備を組み立てて使用しなけ
ればならないために、特に第２図に鎖線で示した仮設部
分の資材及び取り付は解体工数が大きくなって、工期が
長くなるとともに、原子炉の構築作業との相互干渉を生
じ易いという問題点があり、加熱手段３を作動させるた
めに、補助ボイラを運転して加熱蒸気を発生させなけれ
ばならず、コスト上昇を招く等の問題点を生じるもので
あった。However, with this test method, temporary equipment must be assembled and used in parallel with the reactor construction work, which requires special attention to materials and installation for the temporary parts shown by the chain lines in Figure 2. However, in order to operate the heating means 3, an auxiliary boiler must be operated to generate heating steam. This has led to problems such as increased costs.
「発明の目的とその達成手段」
本発明は、このような従来技術の問題点を有効に解決し
て、仮設設備の設置をほとんど不要とするとともに、工
期の短縮、コストの低減等を可能とするものであり、こ
のため、復水供給水系から原子炉圧力容器等に給水し、
該原子炉圧力容器の貯留水の一部を原子炉残留熱除去系
等により循環させるとと６に、該循環用ポンプ及び循環
水のジュール熱によって通水を加熱し、試験適温上昇後
にほう成木注入系用ポンプ等の作動により加圧する如く
しているものである。"Objectives of the Invention and Means for Achieving the Aims" The present invention effectively solves the problems of the prior art, eliminates the need for almost all temporary equipment installation, shortens the construction period, and reduces costs. Therefore, water is supplied from the condensate supply water system to the reactor pressure vessel, etc.
When a part of the water stored in the reactor pressure vessel is circulated through the reactor residual heat removal system, etc., the flowing water is heated by the circulation pump and the Joule heat of the circulating water, and after the temperature rises to the appropriate temperature for the test, the The pressure is applied by operating a wood injection pump or the like.
「実施例」
以下、本発明の原子炉圧力容器及び付属配管の耐圧試験
方法の一実施例を第１図に基づいて説明する。なお、従
来例と共通する部分には、同一符号を付して説明を簡略
化する。"Example" Hereinafter, an example of the pressure test method for a reactor pressure vessel and attached piping according to the present invention will be described based on FIG. 1. Note that parts common to the conventional example are given the same reference numerals to simplify the explanation.
該−実施例においても、給水手段２と加熱手段３と加圧
手段４とをそれぞれ有しているが、これらの手段は、原
子炉に本来設備として設置されているものを組み合わせ
て構成するようにしているものであり、給水手段２は復
水供給水系３０、加熱手段３は原子炉残留熱除去系２８
、加圧手段４はほう成木注入系２９を使用する基本構成
である。This embodiment also has the water supply means 2, heating means 3, and pressurizing means 4, but these means are constructed by combining equipment originally installed in the nuclear reactor. The water supply means 2 is a condensate supply water system 30, and the heating means 3 is a reactor residual heat removal system 28.
, the pressurizing means 4 has a basic configuration using a mature oak injection system 29.
即ち、給水手段２は、原子炉の運転開始前（核加熱開始
前）の状態で、復水供給水系３０における復水貯留タン
ク３１の貯留水を、復水供給水系用ポンプ３２により送
り出して、原子炉残留熱除去系２８の配管の一部と、原
子炉冷却水再循環系１２における吐出配管の一部を経由
させて、原子炉圧力容器ｌの中に矢印で示すように送り
込むものであり、この場合の空気抜き及び溢れた水の処
理は、原子炉圧力容器ｌの上鏡から、ベント配管３３に
よって前記機器ザンブタンク２４に導かれ、原子炉圧力
容器１等の残留空気をなくすようにしている。That is, the water supply means 2 sends out the water stored in the condensate storage tank 31 in the condensate supply water system 30 by the condensate supply water system pump 32 before the start of operation of the nuclear reactor (before the start of nuclear heating). It is sent into the reactor pressure vessel l as shown by the arrow through a part of the piping of the reactor residual heat removal system 28 and a part of the discharge piping of the reactor cooling water recirculation system 12. In this case, the air is vented and the overflowing water is treated by leading the reactor pressure vessel L from the upper mirror to the equipment tank 24 through the vent pipe 33 to eliminate residual air in the reactor pressure vessel 1, etc. .
前記加熱手段３は、給水手段２と加熱手段３の配管との
接続を弁１７によって遮断し、次いで、原子炉残留熱除
去系２８を循環状態として温度上昇を図るものであり、
この場合、原子炉残留熱除去系２８の熱交換器３４を非
運転状態としておいて、原子炉残留熱除去系用ポンプ３
５を運転し、給水手段２によって水張り状態となった原
子炉圧力容器ｌ及びこれに連通している配管に、水を送
り込むとともに、再び原子炉残留熱除去系用ポンプ３５
に戻る循環を行ない、該循環用ポンプ（第１図では原子
炉残留熱除去系用ポンプ３５）のジュール熱及び循環水
の通水によるジュール熱により、循環水の温度を徐々に
上昇させ、目的とする耐圧適温まで導くものである。The heating means 3 shuts off the connection between the water supply means 2 and the piping of the heating means 3 through a valve 17, and then puts the reactor residual heat removal system 28 into a circulating state to raise the temperature.
In this case, the heat exchanger 34 of the reactor residual heat removal system 28 is kept in a non-operating state, and the reactor residual heat removal system pump 3
5 to feed water into the reactor pressure vessel l filled with water by the water supply means 2 and the piping connected thereto, and the reactor residual heat removal system pump 35 is operated again.
The temperature of the circulating water is gradually raised by the Joule heat of the circulation pump (reactor residual heat removal system pump 35 in Figure 1) and the Joule heat of the circulating water. This will lead to the appropriate pressure and temperature.
前記加圧手段は、加熱手段３の実施工程で開放状態とし
た弁１７を閉塞して、はう成木注入系２９のほう成木注
入系用タンク３６に、少量の純水を貯留しておいて、は
う成木注入系用ポンプ３７を運転することにより、加圧
水を矢印で示すように、直接的に原子炉圧力容器ｌの中
に送り込み、耐圧試験を実施するものである。なお、加
圧手段４におけるほう成木注入系用ポンプ３７は、非常
時に原子炉圧力容器１の中にほう成木を送り込む加圧能
力を有しているために、単独で耐圧試験時の圧力発生を
行ない得るものであるが、第１図に鎖線で示すように、
はう成木注入系用ポンプ３７の仕様に応じて、従来例に
準じた仮設のプランジャポンプ１９を設けて、加圧手段
４の補助をさせることもあり得る。または、制御棒駆動
系用ポンプを使用してらよい。The pressurizing means closes the valve 17 that was opened in the step of implementing the heating means 3, and stores a small amount of pure water in the growing mature tree injection system tank 36 of the creeping mature tree injection system 29. Then, by operating the creeping mature tree injection system pump 37, pressurized water is directly sent into the reactor pressure vessel 1 as shown by the arrow, and a pressure test is carried out. It should be noted that the pump 37 for the adult wood injection system in the pressurizing means 4 has the pressurizing ability to feed adult wood into the reactor pressure vessel 1 in an emergency, so it can independently handle the pressure during the pressure test. However, as shown by the chain line in Figure 1,
Depending on the specifications of the creeping mature tree injection system pump 37, a temporary plunger pump 19 similar to the conventional example may be provided to assist the pressurizing means 4. Alternatively, a control rod drive system pump may be used.
なお、本発明は、次の実施態様を包含するものである。Note that the present invention includes the following embodiments.
（１）原子炉残留熱除去系用ポンプ３５の運転による加
熱に加えて、原子炉冷却水再循環系１２における原子炉
冷却水再循環系用ポンプ２２を併用退転して、そのジュ
ール熱により水温を上昇させるようにすること。あるい
は、循環路を形成し得る他のポンプを使用すること。(1) In addition to heating by the operation of the reactor residual heat removal system pump 35, the reactor cooling water recirculation system pump 22 in the reactor cooling water recirculation system 12 is also retracted, and the Joule heat is used to raise the water temperature. to increase the Alternatively, use other pumps that can form a circulation path.
（ｉｉ）給水手段２において、復水供給水系３ｏの使用
により低圧炉心スプレ系２７の配管を使用する等により
給水を行なうこと。(ii) In the water supply means 2, water is supplied by using the condensate supply water system 3o and the piping of the low pressure core spray system 27, etc.
（ｉｉｉ）加圧手段は、はう成木注入系用ポンプに準じ
た高圧を発生し得るものを使用すること。(iii) As the pressurizing means, use one that can generate high pressure similar to that of a pump for a growing tree injection system.
（ｉｖ）原子炉圧力容器１の排水は、原子炉冷却水再循
環系１２または原子炉残留熱除去系２８の配管を経由し
て行なうこと。(iv) The reactor pressure vessel 1 is drained via the reactor cooling water recirculation system 12 or the reactor residual heat removal system 28 piping.
「発明の効果」
以上説明したように、本発明の原子炉再循環系の耐圧試
験方法によれば、次のような効果を奏することができる
。"Effects of the Invention" As explained above, according to the pressure test method for a nuclear reactor recirculation system of the present invention, the following effects can be achieved.
■給水手段と加熱手段と加圧手段とがそれぞれ原子炉の
本設設備を使用して行なわれるため、従来例と比較して
、膨大な仮設設備が不要となり、資材の低減、取り付け
、解体工数の大幅な削減ができる。■Since the water supply means, heating means, and pressurizing means are carried out using the reactor's main equipment, compared to conventional systems, there is no need for a huge amount of temporary equipment, reducing the amount of materials, installation, and dismantling man-hours. can be significantly reduced.
■上記により、据え付は工法が改善されて、工期の短縮
が可能となる。■As a result of the above, the installation method has been improved, making it possible to shorten the construction period.
■加熱手段がポンプのジュール熱を利用するものである
から、補助ボイラの運転が不要となる。■Since the heating means uses the Joule heat of the pump, there is no need to operate an auxiliary boiler.
第１図は本発明における原子炉圧力容器及び付属配管の
耐圧試験方法の一実施例を示す配管系統図、第２図はそ
の耐圧試験方法の従来例を示す配管系統図である。
■・・・・・・原子炉圧力容器、２・・・・・・給水手
段、３・・・・・・加熱手段、４・・・・・・加圧手段
、５・・・・・・純水タンク、６・・・・・・ポンプ、
７・・・・・・濾過水タンク、８・・・・・・ミキシン
グタンク、９・・・・・・蒸気供給系、ＩＯ・・・・・
・仮設配管、１■・・・・・・原子炉格納容器、１２・
・・・・・原子炉冷却水再循環系、１３・・・・・・原
子炉冷却水浄化系、Ｉ４・・・・・仮設配管、１５・・
・・・・主蒸気配管、１６・・・・原子炉隔離時冷却系
、１７・・・・・・弁−１１８・・・・・・分岐配管、
［９・・・・・・プランジャポンプ、２０・・・・・・
ヘッダ、２１・・・・・加圧水ｆＪ’ｌ給管、２２・・
・・・・原子炉冷却水再循環用ポンプ、２３・・・・・
・排水配管、２４・・・・・・機器サンプタンク、２５
・・・・・・給水系、２６・・・・・高圧炉心スプレ系
、２７・・・・・・低圧炉心スプレ系、２８・・・・・
・原子炉残留熱除去系、２９・・・・・・はう成木注入
系、３０・・・・・・復水供給水系、３１・・・・・・
復水貯留タンク、３２・・・・・・復水供給水系用ポン
プ、３３・・・・・・ベント配管、３４・・・・・・熱
交換器、３５・・・・・・原子炉残留熱除去系用ポンプ
、３６・・・・・・はう成木注入系用タンク、３７・・
・・・・はう成木注入系用ポンプ。FIG. 1 is a piping system diagram showing an embodiment of the pressure test method for a reactor pressure vessel and attached piping according to the present invention, and FIG. 2 is a piping system diagram showing a conventional example of the pressure test method. ■... Reactor pressure vessel, 2... Water supply means, 3... Heating means, 4... Pressurizing means, 5... Pure water tank, 6...pump,
7...Filtered water tank, 8...Mixing tank, 9...Steam supply system, IO...
・Temporary piping, 1■・・・Reactor containment vessel, 12・
... Reactor cooling water recirculation system, 13 ... Reactor cooling water purification system, I4 ... Temporary piping, 15 ...
Main steam piping, 16 Reactor isolation cooling system, 17 Valve-118 Branch piping,
[9... Plunger pump, 20...
Header, 21... Pressurized water fJ'l supply pipe, 22...
...Reactor cooling water recirculation pump, 23...
・Drainage piping, 24...Equipment sump tank, 25
...Water supply system, 26...High pressure core spray system, 27...Low pressure core spray system, 28...
・Reactor residual heat removal system, 29... Growing mature tree injection system, 30... Condensate supply water system, 31...
Condensate storage tank, 32...Pump for condensate supply water system, 33...Vent piping, 34...Heat exchanger, 35...Remaining reactor Pump for heat removal system, 36...Tank for creeping mature tree injection system, 37...
...Pump for injection system for creeping mature trees.
Claims (1)
原子炉圧力容器の貯留水の一部を原子炉残留熱除去系等
により循環させるとともに、該循環用ポンプ及び循環水
のジュール熱によって通水を加熱し、試験適温上昇後に
試験圧力まで加圧することを特徴とする原子炉圧力容器
及び付属配管の耐圧試験方法。 （ｉｉ）復水供給水系から原子炉圧力容器等に給水し、
該原子炉圧力容器の貯留水の一部を原子炉残留熱除去系
等により循環させるとともに、該循環用ポンプ及び循環
水のジュール熱によって通水を加熱し、試験適温上昇後
にほう酸水注入系用ポンプ等の作動により加圧水を原子
炉圧力容器に送り、試験圧力まで加圧することを特徴と
する原子炉圧力容器及び付属配管の耐圧試験方法。[Scope of Claims] (i) Water is supplied from the condensate supply water system to the reactor pressure vessel, etc., and part of the water stored in the reactor pressure vessel is circulated through the reactor residual heat removal system, etc. A pressure test method for a reactor pressure vessel and attached piping, which is characterized by heating the water flowing through the pump and circulating water using Joule heat, and pressurizing it to the test pressure after the test temperature rises. (ii) Supply water from the condensate supply water system to the reactor pressure vessel, etc.
Part of the water stored in the reactor pressure vessel is circulated through the reactor residual heat removal system, etc., and the circulating water is heated by the circulation pump and the Joule heat of the circulating water, and after the temperature rises to the appropriate temperature for the test, it is used for the boric acid water injection system. A pressure resistance test method for a reactor pressure vessel and attached piping, which is characterized by sending pressurized water to the reactor pressure vessel by operating a pump, etc., and pressurizing it to the test pressure.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61042315A JPH0756520B2 (en) | 1986-02-27 | 1986-02-27 | Pressure resistance test method for reactor pressure vessel and attached piping |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61042315A JPH0756520B2 (en) | 1986-02-27 | 1986-02-27 | Pressure resistance test method for reactor pressure vessel and attached piping |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62198792A true JPS62198792A (en) | 1987-09-02 |
| JPH0756520B2 JPH0756520B2 (en) | 1995-06-14 |
Family
ID=12632582
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61042315A Expired - Fee Related JPH0756520B2 (en) | 1986-02-27 | 1986-02-27 | Pressure resistance test method for reactor pressure vessel and attached piping |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0756520B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008294493A (en) * | 2007-05-22 | 2008-12-04 | Nippon Hoso Kyokai <Nhk> | Sound quality correcting device for flexible speaker, and speaker system having sound quality correcting device |
-
1986
- 1986-02-27 JP JP61042315A patent/JPH0756520B2/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008294493A (en) * | 2007-05-22 | 2008-12-04 | Nippon Hoso Kyokai <Nhk> | Sound quality correcting device for flexible speaker, and speaker system having sound quality correcting device |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0756520B2 (en) | 1995-06-14 |
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| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |