JP2009002946A - 原子炉の検査、保守及び修理のための装置及び方法 - Google Patents
原子炉の検査、保守及び修理のための装置及び方法 Download PDFInfo
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- JP2009002946A JP2009002946A JP2008153672A JP2008153672A JP2009002946A JP 2009002946 A JP2009002946 A JP 2009002946A JP 2008153672 A JP2008153672 A JP 2008153672A JP 2008153672 A JP2008153672 A JP 2008153672A JP 2009002946 A JP2009002946 A JP 2009002946A
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- 238000007689 inspection Methods 0.000 title claims abstract description 37
- 238000012423 maintenance Methods 0.000 title claims abstract description 32
- 230000008439 repair process Effects 0.000 title claims abstract description 27
- 238000000034 method Methods 0.000 title claims abstract description 21
- 239000012636 effector Substances 0.000 claims abstract description 42
- 230000008878 coupling Effects 0.000 claims abstract description 16
- 238000010168 coupling process Methods 0.000 claims abstract description 16
- 238000005859 coupling reaction Methods 0.000 claims abstract description 16
- 230000008602 contraction Effects 0.000 claims abstract description 11
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 23
- 239000000498 cooling water Substances 0.000 description 6
- 239000000203 mixture Substances 0.000 description 6
- 230000000712 assembly Effects 0.000 description 4
- 238000000429 assembly Methods 0.000 description 4
- 239000002826 coolant Substances 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 230000008859 change Effects 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 238000009760 electrical discharge machining Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 206010073306 Exposure to radiation Diseases 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 238000003491 array Methods 0.000 description 1
- 229910000963 austenitic stainless steel Inorganic materials 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 230000003749 cleanliness Effects 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 238000005507 spraying Methods 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000002604 ultrasonography Methods 0.000 description 1
Images
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
- G21C17/01—Inspection of the inner surfaces of vessels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/207—Assembling, maintenance or repair of reactor components
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
【解決手段】原子炉を検査する装置200は軌道204、アーム202、固定装置206及びエフェクタ208からなる。アーム202は収縮長さ及び伸長長さを有してもよい。伸長長さは収縮長さの2倍を超えてもよい。軌道204はアーム202を移動ためのモータを含む。原子炉の検査、保守又は修理を実行する方法は、装置200を形成するために、固定装置206、軌道204、アーム202及びエフェクタ208を動作自在に結合することと、装置200を原子炉に挿入することと、装置200を原子炉の内部に固定することと、装置200を動作させることとを含む。
【選択図】図2
Description
Claims (10)
- 原子炉の検査、保守又は修理を実行する方法において、
装置(200)を形成するために、固定装置(206)、第1の軌道(204)、アーム(202)及びエフェクタ(208)を動作自在に結合して検査装置(200)を構成する工程と;
前記装置(200)を前記原子炉に挿入する工程と;
前記装置(200)を前記原子炉の内部に固定する工程と;
前記装置(200)を動作させる工程とを有し、
前記アーム(202)は収縮長さを有し、
前記アーム(202)は伸長長さを有し、
前記伸長長さは前記収縮長さの2倍を超えることを特徴とする方法。 - 原子炉を検査する検査装置(200)において、
第1の軌道(204)と;
アーム(202)と;
固定装置(206)と;
エフェクタ(208)とを具備し、
前記アーム(202)は前記第1の軌道(204)に動作自在に結合され、
前記固定装置(206)は前記第1の軌道(204)に動作自在に結合され、
前記エフェクタ(208)は前記アーム(202)に動作自在に結合され、
前記アーム(202)は収縮長さを有し、
前記アーム(202)は伸長長さを有し、
前記伸長長さは前記収縮長さの2倍を超えることを特徴とする検査装置(200)。 - 前記第1の軌道(204)は、前記第1の軌道(204)に対して前記アーム(202)を移動するように構成される1つ以上のモータ(1200、1202、1204)を具備することを特徴とする請求項2記載の装置(200)。
- 前記第1の軌道(204)は、前記第1の軌道(204)に沿って前記アーム(200)を移動するように構成される1つ以上のモータ(1200、1202、1204)を具備することを特徴とする請求項2記載の装置(200)。
- 前記第1の軌道(204)は、前記アーム(202)と前記第1の軌道(204)との動作自在の結合部に対して前記アーム(202)を移動するように構成される1つ以上のモータ(1200、1202、1204)を具備することを特徴とする請求項2記載の装置(200)。
- 前記第1の軌道(204)は、前記第1の軌道(204)に対して前記アーム(202)を回転するように構成される1つ以上のモータ(1200、1202、1204)を具備することを特徴とする請求項2記載の装置(200)。
- ケーブル管理システムを更に具備することを特徴とする請求項2記載の装置(200)。
- 前記アーム(202)は1つ以上の第2の軌道(300)を具備することを特徴とする請求項2記載の装置(200)。
- 前記1つ以上の第2の軌道(300)のうち少なくとも1つは少なくとも3つの部分を含むことを特徴とする請求項8記載の装置(200)。
- 前記エフェクタ(208)は1つ以上のセンサを具備することを特徴とする請求項2記載の装置(200)。
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US11/812,576 US7769123B2 (en) | 2007-06-20 | 2007-06-20 | Inspection, maintenance, and repair apparatuses and methods for nuclear reactors |
US11/812,576 | 2007-06-20 |
Publications (3)
Publication Number | Publication Date |
---|---|
JP2009002946A true JP2009002946A (ja) | 2009-01-08 |
JP2009002946A5 JP2009002946A5 (ja) | 2013-03-28 |
JP5675036B2 JP5675036B2 (ja) | 2015-02-25 |
Family
ID=40136481
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2008153672A Expired - Fee Related JP5675036B2 (ja) | 2007-06-20 | 2008-06-12 | 原子炉の検査、保守及び修理のための装置及び方法 |
Country Status (6)
Country | Link |
---|---|
US (2) | US7769123B2 (ja) |
JP (1) | JP5675036B2 (ja) |
CH (1) | CH702694B1 (ja) |
ES (1) | ES2375988B1 (ja) |
MX (1) | MX2008008150A (ja) |
TW (1) | TWI462118B (ja) |
Cited By (5)
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JP2010243492A (ja) * | 2009-03-31 | 2010-10-28 | Ge-Hitachi Nuclear Energy Americas Llc | 原子炉容器の炉心シュラウドの溶接部を磨き直す伸縮式ツールアセンブリおよび方法 |
JP2011514529A (ja) * | 2008-03-15 | 2011-05-06 | アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング | 容器や水槽の水中に位置する壁部位における損傷箇所の修繕装置 |
KR101501840B1 (ko) * | 2013-09-26 | 2015-03-12 | 한전케이피에스 주식회사 | 원자로 헤드 crdm 노즐의 캐노피씰 용접부 결함 검사장치 |
JP2016510892A (ja) * | 2013-03-15 | 2016-04-11 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | 原子炉の炉心環状部、炉心スプレーおよび給水スパージャ領域の原子炉構成機器を検査する装置および方法 |
JP2020531818A (ja) * | 2017-08-21 | 2020-11-05 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | 検査ツール |
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US8526564B2 (en) | 2010-12-13 | 2013-09-03 | Westinghouse Electric Company Llc | Top guide inspection fixture |
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US9318226B2 (en) | 2012-10-09 | 2016-04-19 | Westinghouse Electric Company Llc | Apparatus and method to inspect, modify, or repair nuclear reactor core shrouds |
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Publication number | Priority date | Publication date | Assignee | Title |
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JP2011514529A (ja) * | 2008-03-15 | 2011-05-06 | アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング | 容器や水槽の水中に位置する壁部位における損傷箇所の修繕装置 |
JP2010243492A (ja) * | 2009-03-31 | 2010-10-28 | Ge-Hitachi Nuclear Energy Americas Llc | 原子炉容器の炉心シュラウドの溶接部を磨き直す伸縮式ツールアセンブリおよび方法 |
JP2016510892A (ja) * | 2013-03-15 | 2016-04-11 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | 原子炉の炉心環状部、炉心スプレーおよび給水スパージャ領域の原子炉構成機器を検査する装置および方法 |
KR101501840B1 (ko) * | 2013-09-26 | 2015-03-12 | 한전케이피에스 주식회사 | 원자로 헤드 crdm 노즐의 캐노피씰 용접부 결함 검사장치 |
JP2020531818A (ja) * | 2017-08-21 | 2020-11-05 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | 検査ツール |
JP7346383B2 (ja) | 2017-08-21 | 2023-09-19 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | 検査ツール |
Also Published As
Publication number | Publication date |
---|---|
CH702694B1 (de) | 2011-08-31 |
JP5675036B2 (ja) | 2015-02-25 |
US20100296617A1 (en) | 2010-11-25 |
ES2375988A1 (es) | 2012-03-08 |
US20080317192A1 (en) | 2008-12-25 |
ES2375988B1 (es) | 2013-01-28 |
US7769123B2 (en) | 2010-08-03 |
US8111802B2 (en) | 2012-02-07 |
TW200915344A (en) | 2009-04-01 |
MX2008008150A (es) | 2009-03-04 |
TWI462118B (zh) | 2014-11-21 |
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