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JP5260410B2 - Method and apparatus for preventive maintenance of in-furnace equipment - Google Patents
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JP5260410B2 - Method and apparatus for preventive maintenance of in-furnace equipment - Google Patents

Method and apparatus for preventive maintenance of in-furnace equipment Download PDF

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JP5260410B2
JP5260410B2 JP2009129794A JP2009129794A JP5260410B2 JP 5260410 B2 JP5260410 B2 JP 5260410B2 JP 2009129794 A JP2009129794 A JP 2009129794A JP 2009129794 A JP2009129794 A JP 2009129794A JP 5260410 B2 JP5260410 B2 JP 5260410B2
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welding
crack
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JP2010276491A (en
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孝一 黒澤
信哉 大森
定史 大友
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Hitachi GE Vernova Nuclear Energy Ltd
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    • 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
    • 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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Description

本発明は、原子力発電プラントにおける原子炉圧力容器内の応力腐食割れに対する予防保全方法に関する。   The present invention relates to a preventive maintenance method for stress corrosion cracking in a reactor pressure vessel in a nuclear power plant.

炉内計装筒等炉内機器の外面溶接部の予防保全方法としては、キャビテーション気泡を含む高圧水を利用するウォータージェットピーニング法(特開2006−201141号公報)が提案されている。このウォータージェットピーニング法は、発生させたキャビテーション気泡崩壊時の衝撃圧を利用して、金属材料表面近傍の残留応力を改善するものである。従来のウォータージェットピーニング法による予防保全工法は、ニッケル基合金(600合金)などの金属材料が高温水中に置かれた場合、その溶接部または溶接部近傍において発生する応力腐食割れ防止法として考案されたものである。応力腐食割れは発生要因として材料,応力,環境の因子が重畳した条件下で生ずるとされており、ウォータージェットピーニング法はこれら三因子の中から応力因子を取り除き応力腐食割れ防止を図った技術である。   As a preventive maintenance method for the outer surface welded portion of the in-furnace equipment such as an in-core instrument tube, a water jet peening method using high pressure water containing cavitation bubbles (Japanese Patent Laid-Open No. 2006-201141) has been proposed. This water jet peening method improves the residual stress in the vicinity of the surface of the metal material by utilizing the generated impact pressure when the cavitation bubble collapses. The conventional preventive maintenance method based on the water jet peening method was devised as a method for preventing stress corrosion cracking that occurs in or near the weld when a metal material such as a nickel-base alloy (600 alloy) is placed in high-temperature water. It is a thing. It is said that stress corrosion cracking occurs under conditions where material, stress, and environmental factors are superimposed as factors of occurrence, and the water jet peening method is a technology that eliminates stress factors from these three factors to prevent stress corrosion cracking. is there.

また、材料因子の観点から耐食性を有した溶接材を使用した肉盛溶接等による表面改質の予防保全方法としては、炉内計装筒内面を対象とした特開2002−90494号公報,原子炉の溶接部等を対象とした特開2001−124888号公報に記載の予防保全方法が提案されている。   Further, as a preventive maintenance method for surface modification by overlay welding using a welding material having corrosion resistance from the viewpoint of material factors, JP 2002-90494 A, Atom A preventive maintenance method described in Japanese Patent Application Laid-Open No. 2001-124888 has been proposed for a welded portion of a furnace.

特開2006−201141号公報JP 2006-141141 A 特開2002−90494号公報JP 2002-90494 A 特開2001−124888号公報JP 2001-124888 A

上述した技術では、原子炉圧力容器の底部に多数林立している炉内計装筒外面の予防保全方法としては効率的に施工できる工法として極めて有効であるが、万一ひびがあった場合の施工については考慮されていない。   The above-mentioned technique is extremely effective as a preventive maintenance method for the outer surface of an in-core instrument tube that stands at the bottom of the reactor pressure vessel. The construction is not considered.

また、炉内計装筒内面を対象とした上述の技術では、炉内計装筒内面の表面改質としては有効な手段であるが、同様に予防保全対象部位のひびの有無について配慮されておらず、万一ひびがあった場合の施工については考慮されていない。   In addition, the above-mentioned technology for the inner surface of the in-core instrumentation cylinder is an effective means for surface modification of the inner surface of the in-core instrumentation cylinder. There is no consideration for construction in the event of a crack.

また、上述した原子炉内の溶接部を対象とした肉盛溶接による表面改質の予防保全方法では、材料面からの記載はあるが、供用期間中の運転プラントを対象とした実際の原子炉炉内構造物に適用する際の施工については配慮されておらず、複雑形状部位に対する施工性,予防保全対象機器が多数存在する場合の、経済性の観点からの工事期間の短縮という面においても配慮されていない。また予防保全対象部位のひびの有無についても配慮されておらず、万一ひびがあった場合の施工については考慮されていない。   Moreover, in the preventive maintenance method of surface modification by overlay welding for the welded portion in the reactor described above, although there is a description from the material aspect, an actual nuclear reactor intended for an operating plant during the service period There is no consideration for construction when applying to the reactor internal structure, and in terms of shortening the construction period from the economical point of view when there are many workable parts for complex shaped parts and preventive maintenance target devices. Not considered. Also, there is no consideration for the presence or absence of cracks in the preventive maintenance target part, and no consideration is given to construction in the event of a crack.

そこで、本願発明が解決しようとする課題は、施工後の信頼性に優れた予防保全工法を提供することにある。   Therefore, the problem to be solved by the present invention is to provide a preventive maintenance method having excellent reliability after construction.

上記課題を解決するため、本発明は原子炉圧力容器の応力腐食割れを耐食性に優れた肉盛り溶接により防止する炉内機器の予防保全方法において、原子炉圧力容器の内面に溶接により取り付けられた炉内機器又は前記原子炉圧力容器の溶接部の検査を行い、前記検査結果により肉盛溶接の条件を変えることを特徴とする。   In order to solve the above-mentioned problems, the present invention is a preventive maintenance method for in-core equipment that prevents stress corrosion cracking of a reactor pressure vessel by build-up welding having excellent corrosion resistance, and is attached to the inner surface of the reactor pressure vessel by welding. Inspecting the in-reactor equipment or the welded portion of the reactor pressure vessel, and changing the build-up welding conditions according to the inspection result.

前記手段により、施工後の信頼性に優れ、工事期間を短縮した予防保全方法を提供できる。
By the above means, it is possible to provide a preventive maintenance method that is excellent in reliability after construction and shortens the construction period .

本発明の一実施例である、予防保全工法フローを示す。The preventive maintenance method flow which is one Example of this invention is shown. 本発明の一実施例である、ひび有無に対する溶接施工図を示す。The welding construction figure with respect to the presence or absence of a crack which is one Example of this invention is shown. 本発明の一実施例である、溶接条件設定フローを示す。The welding condition setting flow which is one Example of this invention is shown. 本発明の一実施例である、き裂進展評価手順を示す。The crack growth evaluation procedure which is one Example of this invention is shown. 本発明の適用対象である、原子炉圧力容器の断面を示す。1 shows a cross section of a reactor pressure vessel to which the present invention is applied. 本発明の一実施例である、表面研磨の装置構成を示す。1 shows an apparatus configuration for surface polishing, which is an embodiment of the present invention. 本発明の一実施例である、溶接の装置構成を示す。The apparatus structure of welding which is one Example of this invention is shown. 本発明の一実施例である、溶接トーチ動作図を示す。The welding torch operation | movement figure which is one Example of this invention is shown. 本発明の一実施例である、浸透探傷検査(PT)の装置構成を示す。1 shows an apparatus configuration of a penetrant flaw inspection (PT) which is an embodiment of the present invention. 本発明の一実施例である、ウォータージェットピーニングの装置構成を示す。1 shows an apparatus configuration of water jet peening according to an embodiment of the present invention. 本発明の一実施例である、水密シールの概要を示す。The outline of the watertight seal which is one example of the present invention is shown. 本発明の一実施例である、局所水密シール付き溶接トーチの装置構成を示す。The apparatus structure of the welding torch with a local watertight seal which is one Example of this invention is shown. 本発明の一実施例である、共通アクセス装置の概要を示す。1 shows an outline of a common access device according to an embodiment of the present invention.

以下、図面を参照して、本発明の実施例を示す。   Embodiments of the present invention will be described below with reference to the drawings.

図1は、本発明の一実施例である肉盛溶接による予防保全工法の作業手順を示すものである。   FIG. 1 shows a work procedure of a preventive maintenance method by overlay welding which is an embodiment of the present invention.

最初に原子炉圧力容器1内の底部に位置する炉内計装筒5溶接部の事前検査を行い、ひびの有無を確認する。事前検査としては、まず目視検査(VT)を実施し、目視検査(VT)により万一ひびが見つかった場合、超音波探傷検査(UT)及び渦流探傷検査(ECT)による詳細検査を行い、ひびの位置,長さおよび深さを特定する。図1では目視検査(VT)を実施する手順を示すが、目視検査(VT)を省略して渦流探傷検査(ECT)によりひび有無の確認と位置の特定を行い、その後、超音波探傷検査(UT)で深さ測定を行う場合もある。これらの事前の検査でひび無しと判断された場合は、溶接部の応力腐食割れの発生を防止するため、表面改質を目的とした予防保全溶接を選択して、次工程である予防保全作業に移る。また、事前検査の結果でひび有りと判断された場合は、ひびの位置,長さおよび深さのデータに基づき、補修を目的とした肉盛溶接を行う基準位置とその基準位置をもとに溶接範囲を設定するとともに、肉盛溶接側へのき裂進展量を評価し肉盛溶接の厚さを設定し、次工程である補修兼予防保全作業に移る。   First, a pre-inspection of the in-core instrument tube 5 weld located at the bottom of the reactor pressure vessel 1 is performed to check for cracks. As a preliminary inspection, a visual inspection (VT) is first performed, and if a crack is found by the visual inspection (VT), a detailed inspection is performed by an ultrasonic inspection (UT) and an eddy current inspection (ECT). Identify the position, length and depth of the. FIG. 1 shows the procedure for carrying out visual inspection (VT). However, visual inspection (VT) is omitted and eddy current inspection (ECT) is performed to confirm the presence or absence of cracks and specify the position, and then ultrasonic inspection ( In some cases, depth measurement is performed by UT). If it is determined that there is no crack in these preliminary inspections, preventive maintenance work, which is the next process, is selected in order to prevent the occurrence of stress corrosion cracking in the weld. Move on. In addition, if it is determined that there is a crack based on the results of the preliminary inspection, based on the reference position for overlay welding for repair purposes and the reference position, based on the data on the position, length and depth of the crack. Set the welding range, evaluate the amount of crack propagation to the build-up welding side, set the thickness of build-up welding, and move on to the next process, repair and preventive maintenance.

次に予防保全作業について炉内機器のうち炉内計装筒の外面溶接部を一例として説明する。なお、ひびなし時の予防保全作業と、ひびあり時の補修兼予防保全作業とでは、同一する作業が多いため、以下まとめて記載する。   Next, the preventive maintenance work will be described by taking the outer surface welded portion of the in-core instrument tube as an example of the in-furnace equipment. The preventive maintenance work when there is no crack and the repair and preventive maintenance work when there is a crack are many of the same work, so they are described collectively below.

まず、対象とする炉内計装筒5の溶接部表面を研磨して表面に付着した酸化皮膜,ゴミ及びクラッド等を除去し、その後、溶接前の形状寸法を予め測定する。次に肉盛溶接を実施する。このときの溶接条件は前記事前検査の結果を反映した条件として、基準位置と溶接範囲及び溶接厚さを設定して溶接作業を行う。溶接終了後に溶接による酸化皮膜の除去のため表面を研磨し、寸法測定装置を使用して溶接部寸法測定を行う。この作業では肉盛厚さの確認も行う。特にひび有りの場合は、前記に示すとおりき裂進展量から肉盛厚さが求められるため、必要な肉盛溶接厚さの要求値を満足していることの確認を行う。その後、浸透探傷検査(PT)または渦流探傷検査(ECT)等により肉盛溶接後の表面検査(溶接後検査)を行い、溶接部近傍の残留応力を低減するためウォータージェットピーニング(WJP)を実施する。   First, the surface of the welded portion of the target in-core instrumentation cylinder 5 is polished to remove oxide film, dust, clad, etc. adhering to the surface, and then the shape dimensions before welding are measured in advance. Next, overlay welding is performed. As welding conditions at this time, a welding operation is performed by setting a reference position, a welding range, and a welding thickness as a condition reflecting the result of the preliminary inspection. After the welding is completed, the surface is polished to remove the oxide film by welding, and the dimensions of the weld are measured using a dimension measuring device. In this operation, the overlay thickness is also checked. In particular, when there is a crack, the build-up thickness is obtained from the crack propagation amount as described above, and therefore it is confirmed that the required value of the build-up weld thickness is satisfied. After that, surface inspection (post-welding inspection) after build-up welding is performed by penetration inspection (PT) or eddy current inspection (ECT), and water jet peening (WJP) is performed to reduce residual stress in the vicinity of the weld. To do.

図2(a)にひび有りの場合の溶接、図2(b)にひび無しの場合の溶接を示す。また、図3に溶接条件設定フローを示す。   FIG. 2 (a) shows welding with cracks, and FIG. 2 (b) shows welding with no cracks. FIG. 3 shows a welding condition setting flow.

ひび有りの場合は、ひび2の存在する範囲全面の肉盛溶接(ひび有り)3を実施する。その際、位置座標は渦流探傷検査(ECT)により取得したデータを使用して設定し、ひび2の長さL1に対して肉盛溶接長さL2は、それよりも広い長さとする。肉盛溶接長さはひび2発生の起点座標と終点座標にそれぞれ一定長さを加算して肉盛溶接開始位置と終了位置の座標を算出し、溶接制御装置に溶接条件として入力する。ここで、肉盛溶接厚さt1は、ひび測定結果に、その後のプラント運転時間を加味して求めたき裂進展評価結果を使用して、プラントの運転期間中に肉盛溶接側にき裂が進展し貫通しない厚さとして設定する。図4にき裂進展評価の手順を示す。評価手順は、初期き裂の設定,負荷条件の設定及び肉盛溶接厚さの設定を行い、その条件に基づいて疲労き裂進展評価を実施する。この評価は肉盛溶接厚さによって変わる。そのため、肉盛り後の疲労き裂進展後のひび長さを考慮した構造全体の破壊評価を行う。肉盛溶接厚さは構造全体破壊評価の範囲内(破壊が起きない範囲)となるように設定する。初期き裂の設定は、事前検査で実施する超音波探傷検査(UT)及び渦流探傷検査(ECT)で得られた結果を利用する。負荷条件の設定は、評価期間中の負荷荷重の繰返し回数を運転実績から設定する。肉盛溶接厚さt1は初期は想定値で実施する。疲労き裂進展評価は、肉盛溶接後の残存き裂に対して負荷条件の設定で求めた繰返し荷重を加えて運転年数に対するき裂進展量を解析により求める。構造全体の破壊評価は、疲労き裂進展評価を考慮したひび長さに対する破壊評価を行い、プラント運転中の全ての供用状態及び地震時に破壊が生じないことを解析により評価する。なお、このき裂進展評価は、発電用原子力設備規格維持規格で公開された手法を用いる。以上の評価結果に基づき、運転年数を想定し、その期間においてき裂の貫通がなく、かつ構造全体に強度を確保可能な肉盛溶接厚さt1を設定する。次に、この肉盛溶接厚さt1に対して、1層当りの溶接厚さから必要となる溶接層数を算出し、溶接電源及び制御装置に溶接条件として入力する。また、ひび2の長さよりも広い長さとする肉盛溶接長さL2は、肉盛溶接厚さt1と同様に疲労き裂進展評価を考慮したひびの長さを求めて、それにひび位置の測定精度、肉盛溶接の位置精度を加算した余長から設定する。   When there is a crack, overlay welding (with crack) 3 is performed on the entire surface where the crack 2 exists. At that time, the position coordinates are set by using data acquired by eddy current inspection (ECT), and the build-up weld length L2 is wider than the length L1 of the crack 2. The build-up welding length is calculated by adding a certain length to the starting point coordinate and the end point coordinate of occurrence of crack 2, and calculating the coordinates of the build-up welding start position and end position, and inputs them to the welding control apparatus as welding conditions. Here, the build-up weld thickness t1 is determined by using the crack growth evaluation result obtained by adding the subsequent plant operation time to the crack measurement result, and the crack is formed on the build-up weld side during the operation period of the plant. Set as a thickness that does not penetrate and penetrate. FIG. 4 shows a procedure for crack growth evaluation. In the evaluation procedure, an initial crack is set, a load condition is set, and a build-up weld thickness is set, and fatigue crack growth evaluation is performed based on the conditions. This evaluation depends on the build-up weld thickness. Therefore, fracture evaluation of the entire structure is performed in consideration of the crack length after fatigue crack growth after build-up. The build-up weld thickness is set so as to be within the range of the overall structure fracture evaluation (a range where fracture does not occur). The initial crack is set by using the results obtained in the ultrasonic inspection (UT) and eddy current inspection (ECT) performed in the preliminary inspection. In setting the load condition, the number of repetitions of the load load during the evaluation period is set from the operation results. The build-up weld thickness t1 is initially set to an assumed value. Fatigue crack growth evaluation is performed by adding the cyclic load obtained by setting the load condition to the residual crack after build-up welding and analyzing the crack growth amount with respect to the operating years. Fracture evaluation of the entire structure is performed for fracture length considering fatigue crack growth evaluation, and it is evaluated by analysis that all the operating conditions during plant operation and that no damage occurs during an earthquake. This crack growth evaluation uses the method disclosed in the nuclear power generation equipment standard maintenance standard. Based on the above evaluation results, the operation years are assumed, and the build-up weld thickness t1 that does not penetrate the crack during that period and can ensure the strength of the entire structure is set. Next, the required number of weld layers is calculated from the weld thickness per layer with respect to the build-up weld thickness t1, and is input as a welding condition to the welding power source and the control device. The build-up weld length L2 that is wider than the length of the crack 2 is the same as the build-up weld thickness t1, and the crack length is determined in consideration of the fatigue crack growth evaluation, and the crack position is measured. It is set from the extra length that adds the accuracy and position accuracy of overlay welding.

ひび無しの場合は、表面改質を目的に肉盛溶接(ひび無し)4を行うもので、肉盛溶接厚さt2は、ひび有りのケースの肉盛溶接側へのき裂進展量を考慮する必要はなく、既設の肉盛対象となる材料の肉盛溶接側への溶接による希釈を考慮すれば良く溶接入熱にもよるが約2kJ/cmの低入熱の場合約1mm程度あれば充分である。この場合肉盛溶接の範囲は、炉内計装筒5の既設溶接部全面及びその溶接熱影響部のカバーする範囲に設定する。なお、ひび有り,ひび無しともに肉盛溶接材としては、従来の600系ニッケル基合金又は690系ニッケル基合金のクラッド溶接に使用している溶接金属の82合金に対して、更に耐食性の優れた52合金を使用する。   When there is no crack, build-up welding (no crack) 4 is performed for the purpose of surface modification, and the build-up weld thickness t2 considers the amount of crack propagation to the build-up welding side of the cracked case There is no need to do this, it is only necessary to consider dilution by welding to the overlay welding side of the material to be built up, and depending on the welding heat input, if the heat input is about 2 kJ / cm, about 1 mm It is enough. In this case, the range of overlay welding is set to the entire surface of the existing welded portion of the in-core instrument tube 5 and the range covered by the weld heat affected zone. In addition, as a build-up welding material with and without cracks, the corrosion resistance of the weld metal 82 alloy used for clad welding of the conventional 600 series nickel base alloy or 690 series nickel base alloy is further improved. 52 alloy is used.

なお、溶接条件は、炉内計装筒5の変形防止を考慮した入熱量とする必要がある。そのため、ひびが無い場合の溶接入熱は、5kJ/cm以下の低入熱、より好ましくは2kJ/cm以下とし、設定範囲の一例としては溶接電流130から175A、電圧8から10V及び溶接速度45から70cm/minがある。また、ひびが確認された場合の溶接は、一般的なインコネルのティグ肉盛溶接に用いられる溶接条件の範囲として約3〜20kJ/cmに着目した結果、約20kJ/cmでは肉盛ビード端にへこみ(アンダーカット)が見られるため、15KJ/cm以下とし、約5〜15kJ/cmを適正な溶接条件範囲と設定した。設定範囲の一例としては溶接電流100から180A、電圧9から11V及び溶接速度8から11cm/minがある。この溶接電流,電圧及び溶接速度を制御装置及び溶接電源に溶接条件として入力する。これにより肉盛ビード端にへこみ等が解消し、変形防止を考慮した信頼性に優れた予防保全方法を提供できる。   Note that the welding condition needs to be a heat input amount in consideration of prevention of deformation of the in-core instrument tube 5. Therefore, the welding heat input when there is no crack is a low heat input of 5 kJ / cm or less, more preferably 2 kJ / cm or less. As an example of the setting range, a welding current of 130 to 175 A, a voltage of 8 to 10 V, and a welding speed of 45 To 70 cm / min. In the case where cracks are confirmed, the welding condition range used for general Inconel TIG overlay welding is about 3 to 20 kJ / cm. As a result, at about 20 kJ / cm, the weld is at the end of the overlay bead. Since dents (undercuts) were observed, it was set to 15 KJ / cm or less, and about 5 to 15 kJ / cm was set as an appropriate welding condition range. Examples of the setting range include a welding current of 100 to 180 A, a voltage of 9 to 11 V, and a welding speed of 8 to 11 cm / min. The welding current, voltage, and welding speed are input to the control device and the welding power source as welding conditions. This eliminates dents and the like at the end of the built-up bead, and can provide a highly reliable preventive maintenance method considering deformation prevention.

ここで上記ティグ溶接は、レーザ溶接に置き換えることも可能である。レーザ溶接の場合は、ティグ溶接の条件である溶接電流,電圧及び溶接速度に対応して、レーザ出力電力(kW=kJ/s),溶接速度(cm/min)により入熱量を設定する。   Here, the TIG welding can be replaced with laser welding. In the case of laser welding, the amount of heat input is set by laser output power (kW = kJ / s) and welding speed (cm / min) corresponding to the welding current, voltage, and welding speed, which are TIG welding conditions.

これら実施例による効果は、施工対象部位の検査を事前に実施して、ひびの有無により肉盛溶接の条件を変えることにより同じ溶接機での予防保全工法の施工が可能であり、ひびの削除などの別な加工機による補修を不要として、万一ひびが発見された場合でも、比較的短期間に補修を兼ねた予防保全を行えることである。また、施工後の信頼性に優れた予防保全方法を提供できる。   The effect of these examples is that the construction of the preventive maintenance method can be performed with the same welding machine by carrying out the inspection of the construction site in advance and changing the overlay welding conditions depending on the presence or absence of cracks. It is possible to carry out preventive maintenance that also serves as a repair in a relatively short period of time, even if a crack is discovered, by eliminating the need for repair using another processing machine. Moreover, the preventive maintenance method excellent in the reliability after construction can be provided.

図5に本工法の対象となる原子炉圧力容器1の断面を示す。   FIG. 5 shows a cross section of the reactor pressure vessel 1 that is the subject of this construction method.

炉内計装筒5は、原子炉圧力容器下鏡6を貫通して多数林立している。予防保全の対象は、原子炉圧力容器下鏡6の貫通部と炉内計装筒5の外周部の溶接部であり、溶接部の形状は、下鏡6の半球面形状を反映し3次元形状となっている。そのため、予防保全作業に使用する装置は、この溶接部の形状に対応する機構を要する。以下に装置例を示す。   A large number of in-core instrumentation cylinders 5 stand through the reactor pressure vessel lower mirror 6. The target of preventive maintenance is the welded portion of the penetration portion of the reactor pressure vessel lower mirror 6 and the outer peripheral portion of the in-core instrument tube 5, and the shape of the welded portion reflects the hemispherical shape of the lower mirror 6 and is three-dimensional. It has a shape. Therefore, a device used for preventive maintenance work requires a mechanism corresponding to the shape of the welded portion. An example of the apparatus is shown below.

図6に表面研磨の一例を示す。   FIG. 6 shows an example of surface polishing.

炉内計装筒5の外周溶接部に研磨砥石11をアクセスする装置として、ヘッド旋回駆動部8とヘッド昇降駆動部9を有する構成において、その先に研磨アーム10及び研磨駆動部12及び研磨砥石11を備える。研磨砥石11は表面に付着した酸化皮膜,ゴミ及びクラッドの除去を目的とし、例えばワイヤブラシ、若しくは不織布に研磨砥粒を均一に塗布・接着した砥石を利用したもので、研磨駆動部12から伝達された回転力により磨き動作を行う。研磨アーム10は炉内計装筒5を基準にその周囲を旋回し、360°の範囲をカバーする。   As a device for accessing the grinding wheel 11 to the outer periphery welded portion of the in-core instrumentation cylinder 5, in a configuration having a head turning drive unit 8 and a head lifting drive unit 9, a polishing arm 10, a polishing drive unit 12 and a grinding wheel are provided at the tip. 11 is provided. The grinding wheel 11 is used for the purpose of removing oxide film, dust and clad adhering to the surface. For example, a grinding wheel in which abrasive grains are uniformly applied and bonded to a wire brush or a non-woven fabric is used. Polishing operation is performed by the rotational force. The polishing arm 10 swivels around the in-furnace instrumentation cylinder 5 as a reference to cover a range of 360 °.

図7に溶接の一例を示す。   FIG. 7 shows an example of welding.

原子炉圧力容器下鏡6から立ち上がる炉内計装筒5の溶接部全面を水密シール19で覆うヘッド構造において、その内部に溶接トーチ17,トーチ首振り動作20の機構,ヘッド旋回動作14及びヘッド昇降動作13の機構と、溶接ワイヤー送り装置18を備える。各機構の運転操作は、原子炉圧力容器上部のオペレーションフロアに設置した各装置により実施するもので、制御装置15b,溶接電源21,冷却水循環装置22、及びカメラコントローラ,モニタ16bより構成される。ここで原子炉圧力容器1内は満水状態であるため、溶接部を局所的に気中環境とするため水密シール19を使用する。   In the head structure in which the entire welded portion of the in-core instrument tube 5 rising from the reactor pressure vessel lower mirror 6 is covered with a watertight seal 19, a welding torch 17, a mechanism of a torch swinging motion 20, a head turning motion 14 and a head are contained therein. The mechanism of the raising / lowering operation | movement 13 and the welding wire feeder 18 are provided. The operation of each mechanism is performed by each device installed on the operation floor above the reactor pressure vessel, and includes a control device 15b, a welding power source 21, a cooling water circulation device 22, a camera controller, and a monitor 16b. Here, since the reactor pressure vessel 1 is in a full water state, a watertight seal 19 is used in order to locally bring the welded portion into the air environment.

本装置は、予め対象物の溶接条件として、前記図4の溶接条件制御フローに示したとおり、ひびの有無に応じて設定した溶接条件の入力値により、装置の駆動動作を制御装置15にて行う。ここで、溶接される位置,範囲の情報は、トーチ首振り動作20,ヘッド旋回動作14及びヘッド昇降動作13の制御に使用され、所定の範囲に溶接トーチ17先端を位置決めして運転される。また、肉盛溶接厚さの情報は、同様にトーチ首振り動作20,ヘッド旋回動作14及びヘッド昇降動作13の制御に使用されるが、ここでは肉盛の層数の条件として設定される。図8(a)及び図8(b)に溶接トーチの動作手順の一例を示す。炉内計装筒5の溶接部45に対して、溶接トーチ17を溶接開始点46に移動し、その位置座標を教示する。引き続き、溶接トーチ17を溶接開始点46に移動し、その位置座標を教示する。教示した溶接開始点46と溶接終了点47の間の補間した経路を作成し、溶接トーチ17を再度溶接開始点46に移動設定し、溶接終了点47の間を肉盛溶接48を実施する。ひび無しの場合は、本動作を炉内計装筒5の円周360°繰返し実施して、溶接部全面を肉盛溶接する。また、ひび有りの場合は、肉盛溶接長さL2に相当する範囲を溶接開始点46と溶接終了点47に設定して実施する。溶接入熱量は、溶接電流,溶接電圧及び溶接速度に係わる条件であり、制御装置15bと溶接電源21に入力される。溶接電流及び溶接電圧は溶接電源21で設定されて、溶接速度は制御装置15bで設定される。予め溶接する位置,範囲の条件から溶接トーチの軌道を計算し、そのときに所定の溶接速度になるようにトーチ首振り動作20,ヘッド旋回動作14及びヘッド昇降動作13の各動作速度に分配されて運転制御する。   As shown in the welding condition control flow in FIG. 4, the present apparatus uses the controller 15 to control the driving operation of the apparatus according to the welding condition input value set according to the presence or absence of cracks. Do. Here, the information on the position and range to be welded is used for controlling the torch swinging motion 20, the head turning motion 14 and the head lifting / lowering motion 13, and is operated by positioning the tip of the welding torch 17 within a predetermined range. Further, the information on the build-up weld thickness is similarly used to control the torch swinging motion 20, the head turning motion 14 and the head lifting / lowering motion 13, but here is set as a condition of the number of layers of the build-up. FIG. 8A and FIG. 8B show an example of the operation procedure of the welding torch. The welding torch 17 is moved to the welding start point 46 with respect to the welded portion 45 of the in-core instrument tube 5, and the position coordinates are taught. Subsequently, the welding torch 17 is moved to the welding start point 46 and the position coordinates are taught. An interpolated path between the taught welding start point 46 and the welding end point 47 is created, the welding torch 17 is moved to the welding start point 46 again, and overlay welding 48 is performed between the welding end points 47. When there is no crack, this operation is repeated 360 ° around the circumference of the in-core instrumentation cylinder 5, and the entire surface of the weld is welded. Further, when there is a crack, the range corresponding to the build-up welding length L2 is set to the welding start point 46 and the welding end point 47, and the process is performed. The welding heat input is a condition related to the welding current, welding voltage, and welding speed, and is input to the control device 15 b and the welding power source 21. The welding current and welding voltage are set by the welding power source 21, and the welding speed is set by the control device 15b. The trajectory of the welding torch is calculated from the conditions of the welding position and range in advance, and is distributed to the respective operating speeds of the torch swinging movement 20, the head turning movement 14 and the head lifting movement 13 so that a predetermined welding speed is obtained at that time. Control the operation.

ここで上記ティグ溶接における構成は、レーザ溶接に置き換えた場合、溶接トーチ17と溶接電源21は、レーザ溶接ノズルとレーザ発信機に対応し、レーザ溶接ノズルとレーザ発信機間の伝送は光ファイバーケーブルで接続することにより、同様にシステムが達成できる。   Here, when the configuration in the TIG welding is replaced with laser welding, the welding torch 17 and the welding power source 21 correspond to the laser welding nozzle and the laser transmitter, and the transmission between the laser welding nozzle and the laser transmitter is an optical fiber cable. By connecting, a system can be achieved as well.

これら実施例による効果は、溶接機に局部気中環境を形成する機能を備えることにより、原子炉圧力容器内に炉水を張った状態で予防保全工事ができ、作業従事者の被ばく低減が可能な予防保全が行えることである。さらに、炉水を張った状態で作業が可能なため工期短縮が図れる。   The effect of these examples is that the welder has a function to create a local air environment, so that preventive maintenance work can be performed with reactor water filled in the reactor pressure vessel, and the exposure of workers can be reduced. That preventive maintenance can be performed. Furthermore, the work period can be shortened because the work can be performed with the reactor water filled.

溶接後の表面研磨は、前記表面研磨の装置と共用する。   Surface polishing after welding is shared with the surface polishing apparatus.

図9に浸透探傷検査(PT)の一例を示す。   FIG. 9 shows an example of a penetrant inspection (PT).

原子炉圧力容器下鏡6から立ち上がる炉内計装筒5の溶接部全面を水密シール19で覆うヘッド構造において、ヘッド旋回駆動部8とヘッド昇降駆動部9を内蔵し、その先に浸透探傷検査(PT)液塗布・洗浄・乾燥ノズルヘッド23と、先端にカメラを有するカメラ(ミラー)首振り機構部25を備える。各機構の運転操作は、原子炉圧力容器上部のオペレーションフロアに設置した各装置により実施するもので、制御装置15c,PT液・洗浄水・エア供給ユニット28,PT液・洗浄水回収ユニット29,乾燥温風供給ユニット30及び観察用カメラ,コントローラ,モニタ16cより構成される。ここで溶接と同様に浸透探傷検査(PT)の検査面を局所的に気中環境とするため水密シールを使用する。   In the head structure in which the entire welded portion of the in-core instrument tube 5 rising from the reactor pressure vessel lower mirror 6 is covered with a water-tight seal 19, a head turning drive unit 8 and a head lifting drive unit 9 are built in, and a penetrant flaw inspection is provided beyond that. A (PT) liquid coating / cleaning / drying nozzle head 23 and a camera (mirror) swing mechanism 25 having a camera at the tip are provided. The operation of each mechanism is performed by each device installed on the operation floor above the reactor pressure vessel. The control device 15c, the PT solution / washing water / air supply unit 28, the PT solution / washing water recovery unit 29, It comprises a dry hot air supply unit 30, an observation camera, a controller, and a monitor 16c. Here, a water-tight seal is used in order to make the inspection surface of the penetrant inspection (PT) locally in the air environment as in the case of welding.

浸透探傷検査(PT)の手順は以下となる。   The procedure of the penetration inspection (PT) is as follows.

第一の手順は溶接面の洗浄である。これは、溶接面にPT液塗布・洗浄・乾燥ノズルヘッド23をヘッド旋回駆動部8とヘッド昇降駆動部9を利用して位置決め後に、洗浄水を噴き付けて前処理洗浄を行う。その後、乾燥温風を送給し、洗浄面の湿分を取り除く。   The first procedure is cleaning of the weld surface. In this method, the PT liquid application / cleaning / drying nozzle head 23 is positioned on the welding surface by using the head turning drive unit 8 and the head lifting / lowering drive unit 9, and then pretreatment cleaning is performed by spraying cleaning water. Then, dry hot air is fed to remove moisture from the cleaning surface.

第二の手順は浸透探傷検査(PT)液塗布である。これは、PT液塗布・洗浄・乾燥ノズルヘッド23を対象部位に位置合わせ後にノズル先端から浸透探傷検査(PT)液を噴き付けて、所定の時間を経過後、次に洗浄液を噴き付けて浸透探傷検査(PT)液を洗い流す。このとき、浸透探傷検査(PT)液と洗浄水は、PT液・洗浄水回収ユニット29により吸引回収する。その後、乾燥温風を送給し、洗浄面の湿分を取り除く。   The second procedure is penetration inspection (PT) solution application. This is because, after positioning the PT liquid application / cleaning / drying nozzle head 23 to the target site, a penetrant flaw detection (PT) liquid is sprayed from the tip of the nozzle, and after a predetermined time has elapsed, the cleaning liquid is then sprayed and penetrated. Rinse the test (PT) solution. At this time, the penetrant flaw detection (PT) liquid and the cleaning water are collected by suction by the PT liquid / cleaning water recovery unit 29. Then, dry hot air is fed to remove moisture from the cleaning surface.

第三の手順は浸透探傷検査(PT)の判定である。これは、溶接面に紫外線(UV)光を当てて、そのときに有意な指示模様がないことを観察カメラを使用して全面を走査し確認する。   The third procedure is a penetration inspection (PT) determination. This is done by irradiating the welding surface with ultraviolet (UV) light and scanning the entire surface using an observation camera to confirm that there is no significant indication pattern at that time.

図10にウォータージェットピーニングの一例を示す。   FIG. 10 shows an example of water jet peening.

ウォータージェットピーニングは、肉盛溶接した部位の残留応力の低減を図るため、炉内計装筒5の肉盛溶接全面を実施する。炉内計装筒5の肉盛溶接部に水噴射ノズル43をアクセスする装置として、ヘッド旋回駆動部8とヘッド昇降駆動部9を有する構成において、その先にノズルアーム49及び水噴射ノズル43を備える。ノズルアーム49は、炉内計装筒5の周囲360°旋回し、ヘッド昇降動作13と水噴射ノズル首振り動作44により水噴射ノズル43の方向と距離を調整して高圧水の噴き付けを行う。なお、ひび無しの場合は、既存の溶接形状に合わせた肉盛溶接となるが、ひび有りの場合は、前述する図2(a)の肉盛溶接厚さt1で部分的に形状が異なるため、肉盛形状に倣った水噴射ノズル43の動作を行う。なお、この動作は肉盛形状の変化点(始点,終点,複数の中間点)の位置座標を予め教示しティーチングプレイバックすることにより達成できる。これにより肉盛溶接した部位の残留応力の低減が可能となる。   Water jet peening is performed on the entire surface of the in-core instrument tube 5 in order to reduce the residual stress in the welded portion. As a device for accessing the water injection nozzle 43 to the built-up welded portion of the in-core instrumentation cylinder 5, in the configuration having the head turning drive unit 8 and the head lifting drive unit 9, the nozzle arm 49 and the water injection nozzle 43 are provided at the tip. Prepare. The nozzle arm 49 rotates 360 ° around the in-core instrument tube 5 and adjusts the direction and distance of the water injection nozzle 43 by the head lifting / lowering operation 13 and the water injection nozzle swinging operation 44 to spray high-pressure water. . In the case where there is no crack, overlay welding is performed in accordance with the existing welding shape. However, in the case where there is a crack, the shape is partially different depending on the overlay welding thickness t1 in FIG. 2A described above. Then, the operation of the water jet nozzle 43 following the overlay shape is performed. This operation can be achieved by teaching in advance the position coordinates of the change point (start point, end point, and a plurality of intermediate points) of the build-up shape and teaching back. As a result, it is possible to reduce the residual stress at the site where overlay welding is performed.

図11に水密シール19の一例を示す。   FIG. 11 shows an example of the watertight seal 19.

本工法のうち溶接,浸透探傷検査(PT)は局所的に気中環境にする必要があるため、水密シールを使用する。このとき炉内計装筒5は原子炉圧力容器下鏡6の球面形状に林立しているため、下鏡面でのシールとの当たりは3次元曲面となり、位置によりその形状が傾斜方向に大きく変化する。この形状は、プラントごとに寸法が変わり、かつ位置によっても変わるため、対象となる炉内計装筒5ごとに準備すると膨大な数量が必要となる。そのため、共通で使用できる構造とするため、以下に示す構造とする。   Among these methods, welding and penetration testing (PT) need to be locally in the air, so a watertight seal is used. At this time, since the in-core instrumentation cylinder 5 stands in the spherical shape of the reactor pressure vessel lower mirror 6, the contact with the seal at the lower mirror surface becomes a three-dimensional curved surface, and its shape changes greatly in the tilt direction depending on the position. To do. Since this shape changes in size for each plant and also changes depending on the position, if it is prepared for each target in-core instrumentation cylinder 5, a huge amount is required. For this reason, in order to obtain a structure that can be used in common, the following structure is adopted.

水密シールは周方向に複数の分割構造とし、各分割面で上下動する機構を有し、自重若しくはシリンダにて炉底部に下端のシール面を押付ける。図11はその一例として幅大6分割及び幅小6分割の計12分割構成とした場合の図である。1分割面には下端に周方向ゴムシール27を有する金属シール板33を有し、金属シール板33の上部にガイドロッド34を設けて、原子炉圧力容器下鏡6の曲率にあわせてガイドロッド34が上下し周方向ゴムシール27を原子炉圧力容器下鏡6に密着させる。なお、1分割面の側面には側面周方向ゴムシール32を設けて、上下動したときでも隙間が生じないように水密性を確保する。   The watertight seal has a plurality of divided structures in the circumferential direction, has a mechanism that moves up and down on each divided surface, and presses the lower seal surface against the furnace bottom by its own weight or cylinder. FIG. 11 is a diagram showing an example in which a total of 12 divisions of 6 wide and 6 wide are used. A metal seal plate 33 having a circumferential rubber seal 27 at the lower end is provided on one divided surface, a guide rod 34 is provided on the upper portion of the metal seal plate 33, and the guide rod 34 is matched to the curvature of the reactor pressure vessel lower mirror 6. Moves up and down to bring the circumferential rubber seal 27 into close contact with the reactor pressure vessel lower mirror 6. In addition, a side surface circumferential rubber seal 32 is provided on the side surface of one divided surface to ensure water tightness so that no gap is generated even when it moves up and down.

本構造において、上部より水密シール19を吊り降ろす際、内部をガスでパージした状態で原子炉圧力容器下鏡6に設定するが、内部の水はパージでは完全に排除はできない。そのため、原子炉圧力容器下鏡6に設定後、パージを継続し、内部の水を完全に排除した後に、溶接若しくは浸透探傷検査(PT)を実施する。   In this structure, when the watertight seal 19 is suspended from the upper part, it is set in the reactor pressure vessel lower mirror 6 with the inside purged with gas, but the water inside cannot be completely removed by purging. Therefore, after setting the reactor pressure vessel lower mirror 6, purging is continued and the internal water is completely removed, and then welding or penetration inspection (PT) is performed.

これら実施例による効果は、肉盛溶接機に原子炉圧力容器下鏡の球Rに追従する伸縮自在なシール機構を備えていることにより、原子炉圧力容器下鏡に多数林立する全ての炉内計装筒外面の予防保全工事を溶接機のシールを変える事無く、一度の炉内設定で多本数の予防保全施工が可能となり、工期の短縮した予防保全が行えることである。   The effect of these embodiments is that the build-up welder is provided with a telescopic seal mechanism that follows the sphere R of the reactor pressure vessel lower mirror, so that many reactors in the reactor pressure vessel lower mirror can be The preventive maintenance work on the outer surface of the instrumentation cylinder can be performed in a single furnace setting without changing the seal of the welding machine, so that a large number of preventive maintenance works can be performed, and the preventive maintenance with a shortened construction period can be performed.

以上の手順及び装置構成は、加圧水型原子炉を一例としているが、沸騰水型原子炉も下鏡に炉内計装筒及び制御棒駆動機構(CRD)ハウジングが貫通し外周部を溶接しており、溶接部の形状は同様に下鏡の半球面形状を反映し3次元形状となっていることから、同様の装置構成により予防保全工法が適用できる。但し、加圧水型原子炉の炉内計装筒5は、図7に示すとおり原子炉圧力容器溶接部から上端までの距離が短く、上方から水密カバーを被せることが可能であるが、沸騰水型原子炉の炉内計装筒5は、炉心中央部付近までの長さを有するため上方から被せることはできない。このような場合は溶接部位を局所的にカバーする方法として図12の実施例がある。図11の実施例では、水密シールを固定して溶接トーチを動かす方法としているが、図12の実施例は、水密シールと溶接トーチを同時に動かす方法とするものであり、本方法により対応可能となる。溶接トーチ17は、先端に局所水密シール50を有するとともに、その内部に溶接電極51と溶接ワイヤーガイド52を有する。なお、局所水密シール50は、押付け面の溶接部の形状に倣い、かつ耐熱性のあるシリコーンスポンジなどが適する。また、側面にはガスパージ供給系53を接続して、常時溶接トーチ17内をガスパージする。前記構造を有する溶接トーチ17において、溶接トーチ17の溶接電極51を溶接開始点46及び溶接終了点47を各々位置座標を教示する。教示した溶接開始点46と溶接終了点47の間の補間した経路を作成し、溶接トーチ17を再度溶接開始点46に移動設定し、ガスパージの流量を上げて局所水密シール50の内部に溜まっている水を排除し、ガス雰囲気に置換後、溶接終了点47までの間を肉盛溶接する。このとき溶接トーチ17の動作は、前述した図7のトーチ首振り動作20の機構,ヘッド旋回動作14及びヘッド昇降動作13の機構と、溶接ワイヤー送り装置18を使用することで達成できる。   The above procedure and apparatus configuration is an example of a pressurized water reactor, but the boiling water reactor also has an inner instrument tube and a control rod drive mechanism (CRD) housing that penetrates the lower mirror and welds the outer periphery. Since the shape of the welded portion is also a three-dimensional shape reflecting the hemispherical shape of the lower mirror, the preventive maintenance method can be applied with the same apparatus configuration. However, the in-core instrument tube 5 of the pressurized water reactor has a short distance from the reactor pressure vessel weld to the upper end as shown in FIG. 7 and can be covered with a watertight cover from above. The in-core instrument tube 5 of the nuclear reactor cannot be covered from above because it has a length up to the vicinity of the central part of the core. In such a case, there is an embodiment shown in FIG. 12 as a method for locally covering the welded portion. In the embodiment of FIG. 11, the watertight seal is fixed and the welding torch is moved. However, the embodiment of FIG. 12 is a method of moving the watertight seal and the welding torch at the same time, and this method can be used. Become. The welding torch 17 has a local water-tight seal 50 at the tip, and a welding electrode 51 and a welding wire guide 52 therein. As the local watertight seal 50, a heat-resistant silicone sponge that follows the shape of the welded portion of the pressing surface is suitable. Further, a gas purge supply system 53 is connected to the side surface so that the inside of the welding torch 17 is always purged with gas. In the welding torch 17 having the above-described structure, the welding electrode 51 of the welding torch 17 is taught the position coordinates of the welding start point 46 and the welding end point 47, respectively. An interpolated path between the taught welding start point 46 and the welding end point 47 is created, the welding torch 17 is moved to the welding start point 46 again, the gas purge flow rate is increased, and the local watertight seal 50 is accumulated. After removing the water and replacing it with a gas atmosphere, build-up welding is performed up to the welding end point 47. At this time, the operation of the welding torch 17 can be achieved by using the mechanism of the torch swing operation 20 of FIG. 7 described above, the mechanism of the head turning operation 14 and the head lifting / lowering operation 13, and the welding wire feeder 18.

これら実施例による効果は、複雑形状部位に対する施工性,予防保全対象機器が多数存在する場合の、経済性の観点からの工事期間の短縮という面においても配慮された予防保全を行えることである。   The effect of these embodiments is that preventive maintenance can be performed in consideration of the shortening of the construction period from the viewpoint of economy when there are many workability and preventive maintenance target devices for complex shaped parts.

次に前記表面研磨,溶接及び浸透探傷検査(PT)を組み合わせて効率よく作業を実施するための装置の一例を図13に示す。これは、加圧水型原子炉を想定した例である。沸騰水型原子炉の場合は、原子炉内は構造物が存在するため、表面研磨,溶接,浸透探傷検査(PT)及びウォータージェットピーニングは、原子炉上部から装置を吊り降ろして、設定することになるが、加圧水型原子炉の場合は、原子炉内の構造物を取り外すことが可能であるため、当該作業時は空間上の制約が大幅に軽減される。この利点を利用して作業性を向上させるための実施例を以下説明する。   Next, FIG. 13 shows an example of an apparatus for efficiently performing work by combining the surface polishing, welding, and penetration inspection (PT). This is an example assuming a pressurized water reactor. In the case of boiling water reactors, there are structures inside the reactor, so surface polishing, welding, penetration flaw detection (PT) and water jet peening should be set by hanging the equipment from the top of the reactor. However, in the case of a pressurized water reactor, since it is possible to remove the structure in the reactor, space constraints are greatly reduced during the operation. An embodiment for improving workability using this advantage will be described below.

炉心支持金物7に設定する共通アクセス装置35は、炉心支持金物7に支持する架台に下げられたテーブル装置40と、テーブル装置40により旋回するアーム装置41と、そのアーム装置41に取り付けられて径方向に移動するヘッド駆動装置42より構成される。   The common access device 35 set in the core support metal 7 includes a table device 40 lowered to a pedestal supported by the core support metal 7, an arm device 41 swiveled by the table device 40, and a diameter attached to the arm device 41. The head driving device 42 moves in the direction.

各種装置ヘッドは、目的に応じて交換し使用するものであり、原子炉上部から吊り降ろし、ヘッド駆動装置42に遠隔で設定する。その際、選択する工法に応じて、使用するヘッドは複数となるが、旋回するアーム装置41とヘッド駆動装置42は、必要台数分を備えたものとする。   Various apparatus heads are exchanged and used according to the purpose, and are suspended from the upper part of the nuclear reactor and set remotely in the head driving apparatus 42. At that time, there are a plurality of heads to be used according to the method to be selected, but it is assumed that the arm device 41 and the head driving device 42 to be swiveled have the necessary number.

補修溶接を実施する場合の一例を以下説明する。   An example of carrying out repair welding will be described below.

十字形状のアーム装置の先に4台有するヘッド駆動装置42に、研磨装置ヘッド36,溶接機ヘッド37,浸透探傷検査(PT)装置ヘッド38及び寸法測定装置ヘッド39を水中遠隔で取り付けて、溶接作業を実施する。補修溶接の手順は、下記のとおりである。   A polishing device head 36, a welder head 37, a penetrant inspection (PT) device head 38, and a dimension measuring device head 39 are attached to a head drive device 42 having four heads of a cross-shaped arm device remotely underwater and welded. Perform the work. The procedure of repair welding is as follows.

第一の手順は溶接部研磨である。これは、溶接部表面に付着している酸化皮膜及びゴミ,クラッドの除去を行う。そのため、研磨装置ヘッド36を目的の炉内計装筒5の座標に、テーブル装置40の旋回動作とヘッド駆動装置42の径方向動作により、位置合わせを行い、溶接部外周全面の磨きを実施する。   The first procedure is welding zone polishing. This removes oxide film, dust, and cladding adhering to the surface of the weld. Therefore, the polishing apparatus head 36 is aligned with the coordinates of the target in-core instrumentation cylinder 5 by the turning operation of the table device 40 and the radial operation of the head drive device 42, and the entire outer periphery of the welded portion is polished. .

第二の手順は溶接である。これは、溶接機ヘッド37を同様に目的の炉内計装筒5の座標に、テーブル装置40の旋回動作とヘッド駆動装置42の径方向動作により、位置合わせを行い、ひび有りの場合はひびの範囲を肉盛溶接、若しくはひび無しの場合は表面改質を目的とした肉盛溶接を行う。   The second procedure is welding. Similarly, the position of the welder head 37 is aligned with the coordinates of the target in-core instrumentation cylinder 5 by the turning operation of the table device 40 and the radial operation of the head drive device 42. In the case where the above range is overlay welding, or when there is no crack, overlay welding for the purpose of surface modification is performed.

第三の手順は浸透探傷検査(PT)である。溶接終了後、浸透探傷検査(PT)装置ヘッド38を目的の炉内計装筒5の座標に、テーブル装置40の旋回動作とヘッド駆動装置42の径方向動作により、位置合わせを行い、溶接面の浸透探傷検査(PT)を行う。   The third procedure is a penetrant inspection (PT). After welding is completed, the penetration inspection (PT) device head 38 is aligned with the coordinates of the target in-core instrumentation cylinder 5 by the turning operation of the table device 40 and the radial operation of the head drive device 42, and the welding surface Perform penetration inspection (PT).

第四の手順は溶接部寸法測定である。浸透探傷検査(PT)終了後、寸法測定装置ヘッド39を目的の炉内計装筒5の座標に、テーブル装置40の旋回動作とヘッド駆動装置42の径方向動作により、位置合わせを行い、溶接厚さを測定する。   The fourth procedure is to measure the weld dimensions. After the penetration inspection (PT) is completed, the dimension measuring device head 39 is aligned with the coordinates of the target in-core instrumentation cylinder 5 by the turning operation of the table device 40 and the radial operation of the head driving device 42, and welding is performed. Measure the thickness.

前記手順に合わせて溶接を実施するもので、なお、各種装置ヘッドの取り付け位置は、手順に合わせて配置するものとする。また、溶接が複数の層に肉盛する場合、その都度浸透探傷検査(PT)を実施することになる。この場合、溶接機ヘッド37と浸透探傷検査(PT)装置ヘッド38を同一装置に有することで、ヘッドの切り替えが短時間で対応可能となり、効率的に作業を実施することが可能となる。すなわち、予防保全工事で使用する溶接機,溶接前後の表面研磨,浸透探傷検査(PT)などの作業を実施する上で、各種作業ヘッドを効率よく切り替えて予防保全施工が可能であり、従って、工期の短縮した予防保全が行える。   Welding is performed according to the above procedure, and the mounting positions of various apparatus heads are arranged according to the procedure. Further, when welding is built up on a plurality of layers, a penetration inspection (PT) is performed each time. In this case, by having the welding machine head 37 and the penetrant flaw detection (PT) apparatus head 38 in the same apparatus, the head can be switched in a short time, and the work can be performed efficiently. In other words, when performing work such as welding machines used in preventive maintenance work, surface polishing before and after welding, and penetration inspection (PT), preventive maintenance work can be performed by efficiently switching various work heads. Preventive maintenance with a shortened construction period can be performed.

これまでひび有無によって溶接条件を変更して肉盛溶接を実施する手順,方法について述べた。それに対して、ひび有りの条件で溶接部全面の表面改質を実施する、事前検査を不要とした予防保全方法も適用可能ある。これは、図1に示す作業手順の目視検査(VT),超音波探傷検査(UT)等の事前検査を省き、予防保全作業としてひび有りの条件に関する補修兼予防保全溶接に相当するステップを実施する方法であり、原子炉圧力容器内の炉内機器の溶接部は多数存在し、炉出力によって異なるが数10本の炉内計装筒を有することを考慮すると、この溶接部全て事前検査に掛かる作業期間を短縮する効果が期待できる。   So far, the procedure and method for performing overlay welding by changing the welding conditions depending on the presence or absence of cracks have been described. On the other hand, it is also possible to apply a preventive maintenance method that does not require prior inspection, in which surface modification is performed on the entire surface of the welded portion under cracked conditions. This eliminates preliminary inspections such as visual inspection (VT) and ultrasonic flaw inspection (UT) of the work procedure shown in FIG. 1, and implements steps corresponding to repair and preventive maintenance welding for cracked conditions as preventive maintenance work In consideration of the fact that there are many welds of in-core equipment in the reactor pressure vessel and there are several tens of in-core instrument tubes depending on the reactor power, all of these welds are pre-inspected. It can be expected to shorten the work period.

本方法は、前記図3の溶接条件フローは、そのまま適用できる。肉盛溶接範囲の算出は、ひび有無に係わらず予防保全を実施する溶接部全面を対象とし、肉盛溶接開始位置,終了位置を算出する。次に肉盛溶接厚さt2は、き裂深さを最大の貫通き裂と想定し疲労き裂進展評価を行い算出し、その結果をもとに肉盛溶接層数を設定する。また、入熱量はひび有りの条件とし、溶接電流,電圧及び溶接速度の算出を行い、各条件を溶接制御装置及び溶接電源に入力する。なお、装置構成はひび有りの方法と同様であるため図6から図10に示す装置構成がそのまま適用可能となる。   In this method, the welding condition flow of FIG. 3 can be applied as it is. The calculation of the overlay welding range is performed on the entire welded portion where preventive maintenance is performed regardless of the presence or absence of cracks, and the overlay welding start position and end position are calculated. Next, the build-up weld thickness t2 is calculated by performing fatigue crack growth evaluation assuming that the crack depth is the maximum penetration crack, and the number of build-up weld layers is set based on the result. Also, the amount of heat input is assumed to be a cracked condition, the welding current, voltage and welding speed are calculated, and each condition is input to the welding control device and the welding power source. Since the apparatus configuration is the same as the method with cracks, the apparatus configuration shown in FIGS. 6 to 10 can be applied as it is.

1 原子炉圧力容器
2 ひび
3 肉盛溶接(ひび有り)
4 肉盛溶接(ひび無し)
5 炉内計装筒
6 原子炉圧力容器下鏡
7 炉心支持金物
8 ヘッド旋回駆動部
9 ヘッド昇降駆動部
10 研磨アーム
11 研磨砥石
12 研磨駆動部
13 ヘッド昇降動作
14 ヘッド旋回動作
15a,15b,15c,15d 制御装置
16a,16d コントローラ,モニタ
16b カメラコントローラ
16c 観察用カメラ,コントローラ,モニタ
17 溶接トーチ
18 溶接ワイヤー送り装置
19 水密シール
20 トーチ首振り動作
21 溶接電源
22 冷却水循環装置
23 PT液塗布・洗浄・乾燥ノズルヘッド
24 PT液・洗浄液回収
25 カメラ(ミラー)首振り機構部
25b カメラ首振り動作
26 乾燥温風供給
27 周方向ゴムシール
28 PT液・洗浄液・エア供給ユニット
29 PT液・洗浄液回収ユニット
30 乾燥温風供給ユニット
31 軸方向ゴムシール
32 側面周方向ゴムシール
33 金属シール板
34 ガイドロッド
35 共通アクセス装置
36 研磨装置ヘッド
37 溶接機ヘッド
38 PT装置ヘッド
39 寸法測定装置ヘッド
40 テーブル装置
41 アーム装置
42 ヘッド駆動装置
43 水噴射ノズル
44 水噴射ノズル首振り動作
45 炉内計装筒溶接部
46 溶接開始点
47 溶接終了点
48 肉盛溶接
49 ノズルアーム
50 局所水密シール
1 Reactor pressure vessel 2 Crack 3 Overlay welding (with crack)
4 Overlay welding (no cracks)
5 In-core instrumentation cylinder 6 Reactor pressure vessel lower mirror 7 Core support hardware 8 Head turning drive unit 9 Head lifting drive unit 10 Polishing arm 11 Polishing wheel 12 Polishing drive unit 13 Head lifting operation 14 Head turning operations 15a, 15b, 15c , 15d Control device 16a, 16d Controller, monitor 16b Camera controller 16c Camera for observation, controller, monitor 17 Welding torch 18 Welding wire feeder 19 Watertight seal 20 Torch swing motion 21 Welding power supply 22 Cooling water circulation device 23 PT liquid application / cleaning Dry nozzle head 24 PT liquid / cleaning liquid recovery 25 Camera (mirror) swing mechanism 25b Camera swing operation 26 Dry hot air supply 27 Circumferential rubber seal 28 PT liquid / cleaning liquid / air supply unit 29 PT liquid / cleaning liquid recovery unit 30 Dry hot air supply unit 31 Axial direction Museal 32 Side circumferential rubber seal 33 Metal seal plate 34 Guide rod 35 Common access device 36 Polishing device head 37 Welding machine head 38 PT device head 39 Dimension measuring device head 40 Table device 41 Arm device 42 Head drive device 43 Water injection nozzle 44 Water Injection nozzle swinging operation 45 In-furnace instrumentation tube welding part 46 Welding start point 47 Welding end point 48 Overlay welding 49 Nozzle arm 50 Local watertight seal

Claims (8)

原子炉圧力容器と炉内機器との溶接部の応力腐食割れを耐食性に優れた部材表面における盛溶接により防止する原子炉圧力容器と炉内機器との溶接部の予防保全方法において、
前記原子炉圧力容器の内面に溶接により取り付けられた前記炉内機器前記原子炉圧力容器の溶接部の検査を行うステップと
その後に、前記検査結果により、前記溶接部のひびが確認されない部分には、所定の厚さで表面改質を目的とした部材表面における肉盛溶接を行い、前記溶接部のひびが確認された部分には、前記ひびの肉盛溶接側へのき裂進展量を考慮した厚さで、前記ひびの補修を兼ねた表面改質を目的とした部材表面における肉盛溶接を行うステップと
前記肉盛溶接を行なう際に、ひびが確認された部分の溶接入熱はひびがない場合よりも高い溶接入熱とすることを特徴とする予防保全方法。
In preventive maintenance method for the weld between the reactor pressure vessel and the furnace device which prevents the meat Mori溶 contact in the reactor pressure vessel and the reactor internal equipments and excellent member surface corrosion resistance to stress corrosion cracking of the weld,
And line Cormorant step testing of the welded portion between the furnace device which is attached by welding to the inner surface of the reactor pressure vessel the reactor pressure vessel,
After that, according to the inspection result , on the portion where the crack of the welded portion is not confirmed, build-up welding is performed on the surface of the member for the purpose of surface modification with a predetermined thickness, and the crack of the welded portion is confirmed. In the part, with a thickness considering the amount of crack propagation to the overlay welding side of the crack, performing the overlay welding on the surface of the member for the purpose of surface modification that also serves as repair of the crack ;
When performing the overlay welding, preventive maintenance how to wherein a welding heat input of cracks was confirmed part of the high heat input than if no cracks.
請求項1に記載の予防保全方法において、In the preventive maintenance method of Claim 1,
前記肉盛溶接の材料は52合金を使用することを特徴とする予防保全方法。The preventive maintenance method according to claim 52, wherein the material for overlay welding uses 52 alloy.
請求項1から請求項2のいずれか一項に記載の予防保全方法において、In the preventive maintenance method as described in any one of Claim 1 to Claim 2,
前記原子炉圧力容器内に炉水を満たした状態で施工することを特徴とする予防保全方法。The preventive maintenance method, wherein the reactor pressure vessel is constructed in a state where reactor water is filled.
請求項1から請求項3のいずれか一項に記載の予防保全方法において、In the preventive maintenance method according to any one of claims 1 to 3,
局部気中環境を形成し、前記肉盛溶接することを特徴とする予防保全方法。A preventive maintenance method comprising forming a local air environment and performing the overlay welding.
請求項1から請求項4のいずれか一項に記載の予防保全方法において、In the preventive maintenance method according to any one of claims 1 to 4,
前記肉盛溶接のステップの後に、前記肉盛溶接範囲を超える領域に対し、噴射ノズルからキャビテーション気泡の発生を伴う高圧水を噴射し残留応力改善を行うことを特徴とする予防保全方法。A preventive maintenance method for improving residual stress by injecting high pressure water accompanied by generation of cavitation bubbles from an injection nozzle to a region exceeding the overlay welding range after the overlay welding step.
請求項4に記載の予防保全方法において、In the preventive maintenance method of Claim 4,
前記局部気中環境は前記原子炉圧力容器下鏡の球Rに伸縮自在なシール機構を追従させることを特徴とする予防保全方法。The preventive maintenance method according to claim 1, wherein the local aerial environment causes the ball R of the reactor pressure vessel lower mirror to follow a telescopic seal mechanism.
原子炉圧力容器内の炉心支持金物に支持するテーブル装置と、前記テーブル装置に固定されて旋回と径方向に駆動するヘッド駆動装置を備えた共通アクセス装置を前記原子炉圧力容器に設置するステップと、Installing in the reactor pressure vessel a common access device comprising a table device supported by a core support metal in the reactor pressure vessel, and a head drive device fixed to the table device and driven to turn and radially. ,
前記共通アクセス装置に設定された検査ヘッドにより、前記原子炉圧力容器の内面に溶接により取り付けられた炉内機器と前記原子炉圧力容器との溶接部の検査行うステップと、Inspecting the welded portion between the reactor pressure vessel and the in-reactor equipment attached to the inner surface of the reactor pressure vessel by the inspection head set in the common access device;
前記共通アクセス装置に設定された溶接機ヘッドにより、前記検査結果より前記溶接部のひびが確認されない部分には、所定の厚さで表面改質を目的とした部材表面における肉盛溶接を行い、前記溶接部のひびが確認された部分には、前記ひびの肉盛溶接側へのき裂進展量を考慮した厚さで、前記ひびの補修を兼ねた表面改質を目的とした部材表面における肉盛溶接を行うステップと、By the welder head set in the common access device, on the part where the crack of the welded portion is not confirmed from the inspection result, build-up welding is performed on the surface of the member for the purpose of surface modification with a predetermined thickness, In the part where the crack of the welded part is confirmed, the thickness of the crack is increased in consideration of the amount of crack propagation toward the build-up weld side of the crack, and on the surface of the member for the purpose of surface modification that also repairs the crack. Performing overlay welding,
前記肉盛溶接を行なう際に、ひびが確認された部分の溶接入熱はひびがない場合よりも高い溶接入熱とすることを特徴とした予防保全方法。A preventive maintenance method characterized in that, when performing build-up welding, the weld heat input at a portion where cracks are confirmed is higher than that when there is no crack.
原子炉圧力容器内の炉心支持金物に支持するテーブル装置と、A table device supported by a core support metal in the reactor pressure vessel;
前記テーブル装置に固定されて旋回と径方向に駆動するヘッド駆動装置を備えた共通アクセス装置と、A common access device having a head drive device fixed to the table device and driven in a turning and radial direction;
前記共通アクセス装置に設定された、前記原子炉圧力容器の内面に溶接により取り付けられた炉内機器と前記原子炉圧力容器との溶接部の検査行う検査ヘッドと、An inspection head that is set in the common access device and inspects a welded portion between the reactor pressure vessel and the in-reactor equipment attached to the inner surface of the reactor pressure vessel by welding,
前記共通アクセス装置に設定された溶接機ヘッドと、A welder head set in the common access device;
前記検査ヘッドにおける検査結果を受信し、前記溶接ヘッドへ前記溶接部のひびが確認されない部分には、所定の厚さで表面改質を目的とした部材表面における肉盛溶接を行い、前記溶接部のひびが確認された部分には、前記ひびの肉盛溶接側へのき裂進展量を考慮した厚さで、前記ひびの補修を兼ねた表面改質を目的とした部材表面における肉盛溶接を行う指示を送信する処理装置と、An inspection result in the inspection head is received, and on the portion where no crack of the welded portion is confirmed on the welding head, overlay welding is performed on the surface of the member for the purpose of surface modification with a predetermined thickness, and the welded portion In the part where the crack is confirmed, the thickness of the crack considering the amount of crack propagation to the overlay welding side of the crack, and the overlay welding on the surface of the member for the purpose of surface modification that also repairs the crack A processing device that transmits an instruction to perform;
前記処理装置は、前記肉盛溶接を行なう際に、ひびが確認された部分の溶接入熱はひびがない場合よりも高い溶接入熱とする予防保全装置。The said processing apparatus is a preventive maintenance apparatus which makes the welding heat input of the part in which the crack confirmed the welding heat input higher than the case where there is no crack when performing the build-up welding.
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