JPH03276098A - Repairing method for nuclear reactor internal structure weld zone - Google Patents
Repairing method for nuclear reactor internal structure weld zoneInfo
- Publication number
- JPH03276098A JPH03276098A JP2078393A JP7839390A JPH03276098A JP H03276098 A JPH03276098 A JP H03276098A JP 2078393 A JP2078393 A JP 2078393A JP 7839390 A JP7839390 A JP 7839390A JP H03276098 A JPH03276098 A JP H03276098A
- Authority
- JP
- Japan
- Prior art keywords
- welding
- structural gap
- internal structure
- weld zone
- thin
- 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.)
- Pending
Links
- 238000000034 method Methods 0.000 title claims description 24
- 238000003466 welding Methods 0.000 claims abstract description 24
- 239000002184 metal Substances 0.000 claims abstract description 19
- 229910052751 metal Inorganic materials 0.000 claims abstract description 19
- 239000011261 inert gas Substances 0.000 claims abstract description 13
- 238000002844 melting Methods 0.000 claims description 3
- 230000008018 melting Effects 0.000 claims description 3
- 230000000903 blocking effect Effects 0.000 claims 1
- 230000007797 corrosion Effects 0.000 abstract description 8
- 238000005260 corrosion Methods 0.000 abstract description 8
- 239000000463 material Substances 0.000 description 9
- 239000011324 bead Substances 0.000 description 8
- 238000005336 cracking Methods 0.000 description 7
- 229910001026 inconel Inorganic materials 0.000 description 4
- 238000007689 inspection Methods 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 230000015572 biosynthetic process Effects 0.000 description 3
- 238000009835 boiling Methods 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 3
- 230000007547 defect Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000012423 maintenance Methods 0.000 description 3
- 230000003449 preventive effect Effects 0.000 description 3
- 239000000470 constituent Substances 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 230000008030 elimination Effects 0.000 description 1
- 238000003379 elimination reaction Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 238000009499 grossing Methods 0.000 description 1
- 229910001055 inconels 600 Inorganic materials 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
- 230000007704 transition Effects 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
- Butt Welding And Welding Of Specific Article (AREA)
- Arc Welding In General (AREA)
Abstract
Description
【発明の詳細な説明】
「産業上の利用分野」
本発明は、原子炉内部構造物溶接部の補修方法に係り、
特に、炉心のシュラウドを囲むバッフルプレートに明Ｉ
ｆられた穴を密閉する閉塞蓋の溶接部の応力腐食割れ等
を防止するものである。DETAILED DESCRIPTION OF THE INVENTION "Field of Industrial Application" The present invention relates to a method for repairing a welded part of a nuclear reactor internal structure,
In particular, the baffle plates surrounding the core shroud were
This prevents stress corrosion cracking of the welded part of the closing lid that seals the hole.
「従来技術」
第４図に示すように、沸騰水型原子炉等の原子炉圧力容
器１の内部には、炉心２、シュラウド３、ンユラウドサ
ポートリング４、バッフルプレート５等が設けられるが
、該バッフルプレート５には、原子炉圧力容器１の内部
構造物の組み立て作業の便を図るために、穴（作業穴・
アクセス中−ル）６が設けられる。"Prior Art" As shown in FIG. 4, inside a reactor pressure vessel 1 such as a boiling water reactor, a reactor core 2, a shroud 3, a cover support ring 4, a baffle plate 5, etc. are provided. The baffle plate 5 is provided with holes (work holes/
(during access) 6 is provided.
そして、各種作業終了後において、第５図に示４−５Ｌ
うに、六６の段部６ａの上に閉塞蓋（アクセスホールカ
バー）７が載置されるとともに、溶接部８を形成して、
作業穴７を密閉するようにしている。この場合、バッフ
ルプレート５及び閉塞蓋７の一溶接開先用壁部７ａの構
成材料を例えばインコネル６００材とし、がっ、溶接材
料を例えばインコネル１８２材とすることにより、溶接
部８の近傍に応力腐食割れ等が発生することを抑制する
ことができる。After completing various works, 4-5L shown in Figure 5 is installed.
In addition, a closing cover (access hole cover) 7 is placed on the stepped portion 6a of the 66, and a welded portion 8 is formed.
The working hole 7 is sealed tightly. In this case, by using Inconel 600 material as the constituent material of one welding groove wall 7a of the baffle plate 5 and the closing lid 7, and using Inconel 182 material as the welding material, the welding groove wall 7a may be made of Inconel 182 material. It is possible to suppress the occurrence of stress corrosion cracking and the like.
「発明が解決しようとする課題」
しかし、前述のインコネル材は、−射的に酸化被膜が薄
いために、応力腐食割れが発生しにくい材料であるが、
穴６の段部６ａと閉塞蓋７の下面縁部（溶接開先用壁部
７ａ ）との間には、金属を相互に接触させた状態の微
小な構造的隙間部９が形成されており、さらに、構造的
隙間部９の部分は、腐食因子である原子炉冷却水が接触
した状態となり、構造的隙間部９が原因で応力腐食割れ
を発生することも考えられる。``Problems to be Solved by the Invention'' However, the above-mentioned Inconel material is a material that is less prone to stress corrosion cracking due to its thin oxide film.
A minute structural gap 9 is formed between the step 6a of the hole 6 and the lower edge of the closing lid 7 (welding groove wall 7a), with the metals in contact with each other. Furthermore, the structural gap 9 comes into contact with the reactor cooling water, which is a corrosive factor, and it is conceivable that stress corrosion cracking may occur due to the structural gap 9.
かかる構造的隙間部９の存在は、予防保全上において好
ましいものではなく、また、閉塞蓋７の溶接部８の近傍
に応力腐食割れが生じた場合の補修方法は、未だ開発さ
れていない。The presence of such a structural gap 9 is not preferable from the viewpoint of preventive maintenance, and a repair method for the case where stress corrosion cracking occurs near the welded portion 8 of the closing lid 7 has not yet been developed.
本発明は、原子炉圧力容器の内部構造物に明けられた穴
を閉塞蓋と溶接とによって閉塞している場合において、
溶接部近傍からの応力腐食割れの発生を低減し、かつ、
原子力発電プラントの長寿命化を図ることを目的とする
ものである。The present invention provides for the case where a hole drilled in the internal structure of a nuclear reactor pressure vessel is closed by a closing cover and welding.
Reduces the occurrence of stress corrosion cracking near the weld, and
The purpose is to extend the life of nuclear power plants.
「課題を解決するための手段と作用」
上記目的を達成するため、原子炉圧力容器の内部構造物
に明けられた穴の段部とその上に載置される閉塞蓋との
間の溶接部を補修する方法であって、段部と閉塞蓋との
接触部分に形成される構造的隙間部の上の溶接金属を薄
肉部を残して除去する工程と、閉塞蓋の裏面を不活性ガ
ス雰囲気とする工程と、薄肉部の上に再度溶接を行なう
ことにより薄肉部と構造的隙間部との部分を熱溶解させ
た後固化状態にする工程と、該固化部分の上に再度溶接
を施して溶接部を形成する工程とを有するもので、構造
上構造的隙間部が形成されている場合、貫通状態となら
ない程度に溶接金属を除去して、薄肉部等を熱溶解させ
ることにより、構造的隙間部を消滅させ、熱溶解部分の
固化後に溶接部が形成されることにより、閉塞蓋及び溶
接部による閉塞が行なわれるものである。"Means and actions for solving the problem" In order to achieve the above purpose, the welded part between the stepped part of the hole drilled in the internal structure of the reactor pressure vessel and the closure lid placed on it. This method includes the steps of removing the weld metal above the structural gap formed at the contact area between the step and the closing lid, leaving only a thin part, and placing the back side of the closing lid in an inert gas atmosphere. a step of welding again on the thin wall portion to thermally melt the portion between the thin wall portion and the structural gap and then solidifying it; and a step of welding again on the solidified portion. If a structural gap is formed in the structure, the weld metal is removed to the extent that no penetration occurs, and thin-walled parts are thermally melted. By eliminating the gap and forming the welded portion after the heat-molten portion has solidified, the closure with the closing lid and the welded portion is performed.
「実施例」
以下、第１図ないし第３図を参照して、本発明に係る原
子炉内部構造物溶接部の補修方法の一実施例を説明する
。"Embodiment" Hereinafter, an embodiment of the method for repairing a welded portion of a nuclear reactor internal structure according to the present invention will be described with reference to FIGS. 1 to 3.
該−実施例にあっても、内部構造物の一つであるバッフ
ルプレート５に、各種作業の便を図るために明けられた
穴（作業穴）６を閉塞蓋７と溶接部８とによって閉塞し
ている構造となっている部分に適用されるもので、穴６
の段部６ａと閉塞蓋７の下面縁部に、微小な構造的隙間
部９が形成されている場合を想定しており、この構造的
隙間部９の補修または予防保全時の処理を技術対象とし
ている。In this embodiment as well, a hole (work hole) 6 made in the baffle plate 5, which is one of the internal structures, to facilitate various operations is closed by a closing lid 7 and a welded part 8. This is applied to the part where the structure is
It is assumed that a minute structural gap 9 is formed between the step 6a and the lower edge of the closing lid 7, and the technical target is to repair or treat this structural gap 9 during preventive maintenance. It is said that
また、第１図は補修作業工程、第２図は全体の補修作業
状況、第３図（Ａ）ないしくＤ）は溶接部近傍の補修作
業の進行状況を示している。Further, FIG. 1 shows the repair work process, FIG. 2 shows the overall repair work situation, and FIGS. 3 (A) to 3D) show the progress of the repair work in the vicinity of the welded part.
以下、第１図ないし第３図に基づき補修作業の工程順に
説明する。Hereinafter, the repair work will be explained in order of steps based on FIGS. 1 to 3.
く内部構造物の取り外し〉
補修作業（または予防保全作業）を行なう場合には、第
２図に示すＸ−Ｙ線よりも上方に位置している部分、つ
まり、原子炉圧力容器１の中に収納されている炉心２及
びシュラウド３よりも上方に位置している内部構造物（
シュラウドヘッド及びセパレータ、蒸気乾燥器等）を取
り外した状態とする。Removal of internal structures> When performing repair work (or preventive maintenance work), it is necessary to remove parts located above the X-Y line shown in Figure 2, that is, inside the reactor pressure vessel 1. Internal structures located above the housed reactor core 2 and shroud 3 (
Shroud head, separator, steam dryer, etc.) are removed.
くノコラウド外の水抜き〉
ツユラウド３の外側でかっバッフルプレート５の上に位
置する円筒状空間１０の原子炉冷却水を排除し、空気雰
囲気とする。なお、シュラウド３の内部及びバッフルプ
レー１・５の下部には、原子炉冷却水が満たされた状態
のままとする。Draining water outside the Kunoco Loud> The reactor cooling water in the cylindrical space 10 located on the large baffle plate 5 outside the Kunoco Loud is removed to create an air atmosphere. Note that the inside of the shroud 3 and the lower part of the baffle plays 1 and 5 remain filled with reactor cooling water.
〈補修用機器の設置〉
第１図において、ステップＩ（Ｓｌ）で示すように、適
宜補修用機器をバッフルプレート５の上方近傍に挿入す
る。該適宜補修用機器とは、後述ずろＳ２ないしＳｌ＋
の各工程を実施するために使用する機器等である。<Installation of Repair Equipment> In FIG. 1, as shown in step I (Sl), appropriate repair equipment is inserted near the upper part of the baffle plate 5. The appropriate repair equipment is Zuro S2 to Sl+, which will be described later.
Equipment, etc. used to carry out each process.
Ｓ２で示すように、補修用機器類の位置の確認が行なわ
れ、不適性（Ｎｏ）の場合には９１に戻り、適性である
場合にはＳ３に移行する。As shown in S2, the position of the repair equipment is confirmed, and if it is unsuitable (No), the process returns to 91, and if it is suitable, the process moves to S3.
Ｓ３で示すように、補修用機器類の位置を確認した後、
シュラウド３の外側や原子炉圧力容器１の内面等に固定
する。As shown in S3, after confirming the location of the repair equipment,
It is fixed to the outside of the shroud 3, the inside of the reactor pressure vessel 1, etc.
〈溶接部の溶接金属の除去〉
Ｓ４と第３図（Ａ）に鎖線で示すように、バッフルプレ
ート５の穴６の段部６ａに載置された閉塞蓋７の溶接開
先用壁部７ａ等に溶接が施されて溶接部８が形成されて
いる場合、段部６ａと溶接開先用壁部７ａとの間に構造
的隙間部９が形成された状態となっており、その上の溶
接金属を除去する工程が実施される。該溶接金属の除去
作業は、例えば遠隔ガウンング技術を適用して、遠隔自
動等により実施される。この場合、閉塞蓋７の溶接部８
の裏面近傍の一部を残して溶接金属の大部分が除去され
る。そして、溶接金属を除去することによって、第３図
（Ｂ）に実線で示すように、当初の閉塞蓋７の溶接開先
用壁部７ａの下面縁部の一部等が寸法Ｔだけ残された状
態の薄肉部１１を形成する。<Removal of weld metal from the welded part> As shown in S4 and the chain line in FIG. When the welded part 8 is formed by welding, etc., a structural gap 9 is formed between the step part 6a and the weld groove wall part 7a, and the A step of removing weld metal is performed. The weld metal removal work is performed remotely and automatically, for example by applying remote gowning technology. In this case, the welded part 8 of the closing lid 7
Most of the weld metal is removed except for a portion near the back surface of the weld metal. By removing the weld metal, a portion of the lower edge of the welding groove wall 7a of the original closing lid 7 remains by a dimension T, as shown by the solid line in FIG. 3(B). The thin-walled portion 11 is formed in a flat state.
該薄肉部１１の寸法Ｔは、例えば１ＩＩＩＩ１１ないし
２＋ｎｍ程度とされる。The dimension T of the thin portion 11 is, for example, about 1III11 to 2+ nm.
く溶接金属除去部分の表面検査〉
Ｓ５で示すように、溶接金属の除去作業後における薄肉
部１１の状態が、上表面側から検査され、Ｎｏの場合は
Ｓ４に戻り、合格した場合はＳ６に移行する。Surface inspection of the weld metal removed part> As shown in S5, the state of the thin wall part 11 after the weld metal removal work is inspected from the upper surface side, and if the result is No, the process returns to S4, and if it passes, the process proceeds to S6. Transition.
〈不活性ガスの注入〉
Ｓ６と第２図とに示すように、バッフルプレート５の下
方に、アルゴンガス等の不活性ガス導入チューブ１２が
挿入されて、バッフルプレート５の下部に不活性ガスが
吹き込まれ、注入された不活性ガスが溜まることにより
、閉塞蓋７の裏面が不活性ガス雰囲気１３となる。<Injection of inert gas> As shown in S6 and FIG. The inert gas that has been blown and injected accumulates, so that the back surface of the closing lid 7 becomes an inert gas atmosphere 13.
〈構造的隙間部の溶解及び固化〉
Ｓ７と第３図（Ｂ）の鎖線とで示すように、薄肉部１１
の上に、溶接材料を例えばインコネル！８２材とする溶
接が、ＴＩＧ溶接等によって施される。該溶接作業は、
特にそのビード初層８ａの溶接入熱が、通常（２層目以
後のピード）の溶接入熱よりも大きくなるように設定さ
れる。このような設定と、不活性ガス雰囲気１３の存在
に基づく保温効果とにより、薄肉部１１と段部６ａの表
面の一部とが熱溶解させられ、ビード初層８ａとともに
溶は込んだ状態となり、そして、溶融金属の落下が不活
性ガス雰囲気１３のガス圧によって抑制される。<Dissolution and solidification of structural gaps> As shown by S7 and the chain line in FIG. 3(B), the thin wall portion 11
For example, use Inconel as a welding material on top! 82 material is welded by TIG welding or the like. The welding work is
In particular, the welding heat input of the first layer 8a of the bead is set to be larger than the normal welding heat input (peeds of the second and subsequent layers). Due to such a setting and the heat retention effect based on the presence of the inert gas atmosphere 13, the thin wall portion 11 and a part of the surface of the stepped portion 6a are thermally melted, and are in a state of melting together with the bead initial layer 8a. , and the falling of the molten metal is suppressed by the gas pressure of the inert gas atmosphere 13.
また、ビード初層８ａの形成の進行とともに、溶融状態
のビード初層８ａが冷却されて固化状態となり、閉塞蓋
７と段部６ａとの残りの接触部分の移動を抑制する。Further, as the formation of the bead initial layer 8a progresses, the molten bead initial layer 8a is cooled and solidified, thereby suppressing movement of the remaining contact portion between the closing lid 7 and the stepped portion 6a.
〈構造上構造的隙間部消滅の検査〉
Ｓ８で示すように、ビード初層８ａの形成後の状態が検
査され、Ｎｏの場合にはＳ７に戻り、合格した場合には
Ｓ９に移行する。<Inspection for elimination of structural gaps> As shown in S8, the state of the bead initial layer 8a after its formation is inspected, and if the result is No, the process returns to S7, and if it passes, the process moves to S9.
く溶接部の形成〉
Ｓ９と第３図（Ｃ）の鎖線とで示すように、ビード初層
８ａの固化部分の上に、２層以下のビートを順次重畳し
て、再度溶接部８を形成する工程が実施される。Formation of a welded part> As shown by S9 and the chain line in FIG. 3(C), two or less layers of bead are sequentially superimposed on the solidified part of the initial bead layer 8a to form the welded part 8 again. A process is performed.
〈表面仕上げ処理〉
ＳＩＯに示すように、溶接部８の表面を平滑化する等の
仕下げ加工が行なわれ、第３図（Ｄ）に示す状態とする
。<Surface Finishing Treatment> As shown in SIO, finishing processing such as smoothing the surface of the welded portion 8 is performed to obtain the state shown in FIG. 3(D).
く最終検査〉
Ｓｌ！で示すように、溶接部８の検査が行なわれ、表面
の仕上げ加工が不十分な場合には８１０に戻り、溶接部
８の内部に欠陥が存在する等の不具合が認められる場合
には、Ｓ４に戻って溶接金属の再度除去等の工程が繰り
返される。そして、溶接部８の検査が合格した場合には
、Ｓ１２に移行する。Final inspection> Sl! As shown in , the welded part 8 is inspected, and if the surface finishing is insufficient, the process returns to 810, and if a defect such as a defect is found inside the welded part 8, the process returns to step S4. Then, the weld metal is removed again and the process is repeated. If the inspection of the welded portion 8 passes, the process moves to S12.
〈補修作業完了及び機器類の撤去〉
Ｓ＋２において、溶接部８の補修作業に使用した機器類
の撤去が行なわれ、かつ、原子炉を当初の状態に戻すこ
とにより補修作業完了となる。<Completion of repair work and removal of equipment> At S+2, the equipment used for repair work on welded section 8 was removed, and the repair work was completed by returning the reactor to its original state.
なお、ここまで説明した一実施例では、バッフルプレー
ト５に明けられた穴６に取り付けられる閉７Ｘ蓋７の溶
接部８を補修対象としたが、原子炉圧力容器１の内部構
造物に明けられた各種の大川閉塞蓋の溶接部を補修対象
として実施することができる。In the embodiment described so far, the welded part 8 of the closed 7X lid 7 attached to the hole 6 made in the baffle plate 5 was targeted for repair. This can be carried out to repair the welded parts of various Okawa blockage covers.
「発明の効果」
以上説明したように、本発明に係る原子炉内部構造物溶
接部の補修方法では、溶接部に構造的隙間部がある場合
に、構造的隙間部の上に薄肉部を残すように溶接金属を
除去し、薄肉部の裏面に不活性ガスを介在させた状態で
、薄肉部の上に再度溶接を行なうことにより、薄肉部と
構造的隙間部との部分を熱溶解させるものであるから、
不活性ガス側の圧力を薄肉部の上方雰囲気の圧力より高
くすることにより、薄肉部等の熱溶解時における溶解金
属落下を防止しながら構造的隙間部を確実に除去して、
溶接部の応力腐食割れ等の欠陥の発生を防止するととも
に、原子力発電プラントの長寿命化を図ることができる
等の効果を奏するものである。"Effects of the Invention" As explained above, in the method for repairing a welded part of a nuclear reactor internal structure according to the present invention, when there is a structural gap in the welded part, a thin wall part is left above the structural gap. The part between the thin wall part and the structural gap is thermally melted by removing the weld metal and performing welding again on the thin wall part with inert gas interposed on the back side of the thin wall part. Because it is,
By making the pressure on the inert gas side higher than the pressure in the atmosphere above the thin-walled parts, structural gaps can be reliably removed while preventing molten metal from falling during hot melting of thin-walled parts.
This has the effect of preventing the occurrence of defects such as stress corrosion cracking in welded parts and extending the life of nuclear power plants.
第１図ないし第３図は本発明に係る原子炉内部構造物溶
接部の補修方法の一実施例を示すもので、第１図は補修
作業工程のフローチャート、第２図は沸騰水型原子炉に
おける補修作業の実施状況の概略を示す正断面図、第３
図（Ａ）ないしくＤ）は第２図の鎖線■部分の補修作業
状況の工程順を示す正断面図、第４図は沸騰水型原子炉
の例を示す正断面図、第５図は第４図に鎖線■で示す部
分の拡大断面図である。
■・・・・・・原子炉圧力容器、
２・・・・炉心、
３・・・・・・ンユラウド、
４・・・・・シュラウドサポートリング、５・・・・・
バッフルプレート、
６・・・・・・穴（作業穴・アクセスホール）、６ａ・
・・・段部、
７・・・・・・閉塞Ｍ（アクセスホールカバー）、７ａ
・・・・・・溶接開先用壁部、
８・・・・・・溶接部、
８ａ・・・・・・ビード初層、
９・・・・・・構造的隙間部、
ｌＯ・・・・・・円筒状空間、
１１・・・・・・薄肉部、
１２・・・・・不活性ガス導入チューブ、１３・・・・
不活性ガス雰囲気。Figures 1 to 3 show an embodiment of the method for repairing a welded part of a nuclear reactor internal structure according to the present invention. Figure 1 is a flow chart of the repair work process, and Figure 2 is a boiling water reactor reactor. A front sectional view showing an outline of the implementation status of repair work in 3rd section.
Figures (A) to D) are front sectional views showing the process order of the repair work in the dashed line ■ part of Figure 2, Figure 4 is a front sectional view showing an example of a boiling water reactor, and Figure 5 is FIG. 4 is an enlarged sectional view of the portion indicated by the chain line ■ in FIG. 4. ■... Reactor pressure vessel, 2... Reactor core, 3... Nyuroud, 4... Shroud support ring, 5...
Baffle plate, 6...hole (work hole/access hole), 6a.
...Stepped portion, 7...Closure M (access hole cover), 7a
・・・・・・Wall part for welding groove, 8・・・・・・Welding part, 8a：・・・Bead first layer, 9：Structural gap part, 1O・・・... Cylindrical space, 11 ... Thin wall part, 12 ... Inert gas introduction tube, 13 ...
Inert gas atmosphere.
Claims (1)
の上に載置される閉塞蓋との間の溶接部を補修する方法
であって、段部と閉塞蓋との接触部分に形成される構造
的隙間部の上の溶接金属を薄肉部を残して除去する工程
と、閉塞蓋の裏面を不活性ガス雰囲気とする工程と、薄
肉部の上に再度溶接を行なうことにより薄肉部と構造的
隙間部との部分を熱溶解させた後固化状態にする工程と
、該固化部分の上に再度溶接を施して溶接部を形成する
工程とを有することを特徴とする原子炉内部構造物溶接
部の補修方法。A method for repairing a weld between a stepped part of a hole drilled in the internal structure of a reactor pressure vessel and a blocking lid placed on it, the method comprising: The thin wall area is removed by removing the weld metal above the formed structural gap leaving the thin wall area, creating an inert gas atmosphere on the back side of the closing lid, and re-welding on the thin wall area. A nuclear reactor internal structure characterized by comprising the steps of thermally melting a portion between the solidified portion and the structural gap portion and then solidifying the portion, and welding again on the solidified portion to form a welded portion. How to repair welded parts of objects.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2078393A JPH03276098A (en) | 1990-03-27 | 1990-03-27 | Repairing method for nuclear reactor internal structure weld zone |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2078393A JPH03276098A (en) | 1990-03-27 | 1990-03-27 | Repairing method for nuclear reactor internal structure weld zone |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH03276098A true JPH03276098A (en) | 1991-12-06 |
Family
ID=13660771
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2078393A Pending JPH03276098A (en) | 1990-03-27 | 1990-03-27 | Repairing method for nuclear reactor internal structure weld zone |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH03276098A (en) |
-
1990
- 1990-03-27 JP JP2078393A patent/JPH03276098A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US20150034266A1 (en) | Building and repair of hollow components | |
| CA2056527C (en) | Fabrication of cast articles from high melting temperature superalloy compositions | |
| EP2373456B1 (en) | Method of repairing a metallic artefact | |
| CN112338624A (en) | Method for preventing large-scale complex part cutting foreign matter residue | |
| JP3079902B2 (en) | Welding repair method for reactor internals | |
| CN109175232A (en) | A kind of thin-walled pressure-bearing casting lost wax casting technique | |
| US5175411A (en) | Method for welding structural gaps | |
| JPH03276098A (en) | Repairing method for nuclear reactor internal structure weld zone | |
| US5494539A (en) | Metal member quality improving method by spot welding | |
| US3934107A (en) | Process for repairing slag ladles | |
| EP2808487B1 (en) | Method for closing an aperture on a blade of a gas turbine | |
| CA1110036A (en) | Repair of bottle top moulds | |
| JPH06289183A (en) | Repair of structure in nuclear reactor | |
| US4598727A (en) | Method of removing chips from the end portion of an upwardly extending conduit | |
| JP2595114B2 (en) | Preventive maintenance of neutron flux monitor housing | |
| JP4488591B2 (en) | Maintenance method of core spare purger | |
| JP7165073B2 (en) | LASER WELDING METHOD FOR DIE CASTING MEMBER AND METHOD FOR MANUFACTURING DIE CASTING PRODUCTS | |
| JPS6055236B2 (en) | Repair welding method for non-ferrous alloys | |
| JPS5914055Y2 (en) | Copper water cooling tab material for electroslag welding | |
| JPH01205892A (en) | Method for welding high carbon steel | |
| JPH10249565A (en) | Piercing method of casting with using core | |
| JP2004351471A (en) | Method for preventing corrosion and device for forming anti-corrosive coating film | |
| JPS6171156A (en) | Repairing method of casting mold | |
| JPH06335792A (en) | Method for repairing cracking | |
| JPH1034374A (en) | Method for generating residual compressive stress in stainless steel and ni-based superalloy, and method for repairing stress corrosion crack by underwater welding |