JP2012507696A - 核燃料の被覆管除去方法と被覆管変形による破砕装置 - Google Patents
核燃料の被覆管除去方法と被覆管変形による破砕装置 Download PDFInfo
- Publication number
- JP2012507696A JP2012507696A JP2011533770A JP2011533770A JP2012507696A JP 2012507696 A JP2012507696 A JP 2012507696A JP 2011533770 A JP2011533770 A JP 2011533770A JP 2011533770 A JP2011533770 A JP 2011533770A JP 2012507696 A JP2012507696 A JP 2012507696A
- Authority
- JP
- Japan
- Prior art keywords
- cladding tube
- fuel
- cladding
- roller
- ovalization
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- 238000005253 cladding Methods 0.000 title claims abstract description 116
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 15
- 238000000034 method Methods 0.000 title claims description 15
- 239000000446 fuel Substances 0.000 claims abstract description 43
- 238000009795 derivation Methods 0.000 claims description 5
- 238000003780 insertion Methods 0.000 claims description 2
- 230000037431 insertion Effects 0.000 claims description 2
- 230000002093 peripheral effect Effects 0.000 claims description 2
- 239000008188 pellet Substances 0.000 abstract description 15
- 230000008439 repair process Effects 0.000 abstract description 2
- 230000007423 decrease Effects 0.000 abstract 1
- 230000008859 change Effects 0.000 description 5
- 230000009467 reduction Effects 0.000 description 5
- 238000004090 dissolution Methods 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 239000011248 coating agent Substances 0.000 description 2
- 238000000576 coating method Methods 0.000 description 2
- 238000005520 cutting process Methods 0.000 description 2
- 238000013467 fragmentation Methods 0.000 description 2
- 238000006062 fragmentation reaction Methods 0.000 description 2
- 239000000843 powder Substances 0.000 description 2
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012634 fragment Substances 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 230000006698 induction Effects 0.000 description 1
- 230000001788 irregular Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000003801 milling Methods 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 230000010355 oscillation Effects 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000002123 temporal effect Effects 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 0.000 description 1
- 230000003313 weakening effect Effects 0.000 description 1
Classifications
-
- 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
- G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
- G21C19/36—Mechanical means only
-
- 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
- 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)
- Solid Fuels And Fuel-Associated Substances (AREA)
- Crushing And Grinding (AREA)
Abstract
【選択図】図1
Description
Claims (8)
- 円形被覆管からの核燃料の除去方法であって、
前記燃料は圧縮状態にあり、
前記被覆管の塑性変形を可能にする多数の周期に亘る反復楕円化により前記被覆管を変形させる装置への前記被覆管の挿入から成るステップを含み、
前記周期に亘る楕円化が、前記燃料を破砕して、その後前記被覆管を元の円形に修復するように、ある周期から他の周期で次第に強くなり、続いて次第に弱まること、
を特徴とする。 - 前記燃料が、少なくとも40周期に亘り、破砕されること、
を特徴とする請求項1に記載の核燃料の被覆管除去方法。 - 楕円化が、圧縮状態での前記燃料の直径を少なくとも3%低減させること、
を特徴とする請求項1または2に記載の核燃料の被覆管除去方法。 - 燃料被覆管(16)の変形を行う装置であって、対向ローラー(3)一対と、前記ローラーを回転するモータ(2)とを含み、
前記ローラーは、円錐誘導部位(10)および円錐導出部位(12)を備えた周辺端部(9)を含み、前記誘導部位(10)および前記導出部位(12)双方は前記ローラーの中央部位に向かって延びるとともに、前記ローラーは、前記装置を通る前記被覆管の進行方向に基本的に平行な回転軸を有し、前記ローラーの前記端部の前記部位全ては、前記被覆管の変形に寄与すること、を特徴とする。 - 前記中央部位が円筒形であること、
を特徴とする請求項4に記載の装置。 - 前記ローラーが、前記方向に対向して傾く回転軸を有すること、
を特徴とする請求項4または5に記載の装置。 - 前記各ローラーが、前記方向に対して、わずか2°しか傾かないこと、
を特徴とする請求項6に記載の装置。 - 装置が、水平方向に対して傾く被覆管ガイドを含むこと、
を特徴とする請求項4〜7のいずれか1項に記載の装置。
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR0857550 | 2008-11-06 | ||
FR0857550A FR2938110B1 (fr) | 2008-11-06 | 2008-11-06 | Procede de vidage de gaines de combustible nucleaire et machine de broyage par deformation de la gaine |
PCT/EP2009/064736 WO2010052298A1 (fr) | 2008-11-06 | 2009-11-06 | Procede de vidage de gaines de combustible nucleaire et machine de broyage par deformation de la gaine |
Publications (2)
Publication Number | Publication Date |
---|---|
JP2012507696A true JP2012507696A (ja) | 2012-03-29 |
JP5548689B2 JP5548689B2 (ja) | 2014-07-16 |
Family
ID=40444830
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2011533770A Expired - Fee Related JP5548689B2 (ja) | 2008-11-06 | 2009-11-06 | 核燃料の被覆管除去方法と被覆管変形による破砕装置 |
Country Status (8)
Country | Link |
---|---|
US (1) | US8708258B2 (ja) |
EP (1) | EP2345041B1 (ja) |
JP (1) | JP5548689B2 (ja) |
CN (1) | CN102203881B (ja) |
FR (1) | FR2938110B1 (ja) |
RU (1) | RU2506658C2 (ja) |
WO (1) | WO2010052298A1 (ja) |
ZA (1) | ZA201103110B (ja) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR101411766B1 (ko) * | 2012-11-30 | 2014-06-25 | 한국수력원자력 주식회사 | 사용후핵연료봉 탈피복장치 |
CN104409121B (zh) * | 2014-12-11 | 2016-09-28 | 中国核动力研究设计院 | 一种弥散燃料板制备中的机械脱钢套方法 |
FR3053151B1 (fr) | 2016-06-23 | 2018-08-10 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Procede de dissolution d'un combustible nucleaire |
CN111799007A (zh) * | 2020-07-16 | 2020-10-20 | 中国核动力研究设计院 | 一种乏燃料燃料棒芯块拆卸装置及拆卸方法 |
CN112670005B (zh) * | 2020-12-18 | 2022-10-21 | 中广核研究院有限公司 | 乏燃料棒处理方法 |
Citations (6)
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JPS56104294A (en) * | 1980-01-09 | 1981-08-19 | Atomic Energy Authority Uk | Method of recovering |
JPS604890A (ja) * | 1983-06-23 | 1985-01-11 | 株式会社日立製作所 | セラミツク核燃料再処理における前処理方法 |
JPS6118895A (ja) * | 1984-07-05 | 1986-01-27 | 株式会社神戸製鋼所 | 使用済核燃料棒の分解方法 |
JPS61119330A (ja) * | 1984-11-14 | 1986-06-06 | テーハー、キーゼルリング、ウント、アルブレヒト、ゲゼルシヤフト、ミツト、ベシユレンクテル、ハフツング、ウント、コンパニ | 傾斜ローラくせ取り機 |
JPS63182599A (ja) * | 1987-01-26 | 1988-07-27 | 株式会社神戸製鋼所 | 使用済燃料の脱被覆方法 |
JP2005043331A (ja) * | 2003-07-09 | 2005-02-17 | Japan Nuclear Cycle Development Inst States Of Projects | 使用済核燃料の脱被覆方法及び脱被覆装置 |
Family Cites Families (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1452479A (fr) * | 1965-11-02 | 1966-02-25 | Atomic Energy Authority Uk | Procédé pour enlever les gaines des cartouches de combustible nucléaire irradiées |
FR2472250A1 (fr) * | 1979-12-20 | 1981-06-26 | Nukem Gmbh | Procede et dispositif pour sortir des matieres combustibles nucleaires de leurs tubes de gainage |
EP0169629A3 (en) * | 1984-07-05 | 1986-09-24 | Kabushiki Kaisha Kobe Seiko Sho | Cladding separation method for a spent nuclear fuel rod |
HUT48046A (en) | 1987-01-21 | 1989-04-28 | Banki Donat Gepipari Mueszaki | Method and device for wrecking magazines for holding specimen irradiated in nuclear power plant |
DE3710193C1 (de) * | 1987-03-27 | 1988-05-19 | Mannesmann Ag | Verfahren zum Herstellen nahtloser Rohre ueber 200 mm Durchmesser und Vorrichtung zur Durchfuehrung des Verfahrens |
US5699690A (en) * | 1995-06-19 | 1997-12-23 | Sumitomo Metal Industries, Ltd. | Method and apparatus for manufacturing hollow steel bars |
JPH1010284A (ja) * | 1996-06-20 | 1998-01-16 | Mitsubishi Heavy Ind Ltd | 使用済み原子燃料の脱被覆方法 |
AT406644B (de) * | 1997-11-14 | 2000-07-25 | Voest Alpine Ind Anlagen | Präzisionswalzverfahren |
RU2145125C1 (ru) * | 1998-03-30 | 2000-01-27 | Производственное объединение "МАЯК" | Устройство для измельчения отработавшего ядерного топлива |
KR100347107B1 (ko) * | 1999-10-28 | 2002-07-31 | 한국전력공사 | 원전연료 펠릿의 탈피복 방법 및 장치 |
RU2216800C2 (ru) * | 2001-12-06 | 2003-11-20 | Центральное конструкторское бюро машиностроения | Агрегат для измельчения длинномерных радиоактивных элементов |
-
2008
- 2008-11-06 FR FR0857550A patent/FR2938110B1/fr not_active Expired - Fee Related
-
2009
- 2009-11-06 EP EP09744702.3A patent/EP2345041B1/fr active Active
- 2009-11-06 JP JP2011533770A patent/JP5548689B2/ja not_active Expired - Fee Related
- 2009-11-06 RU RU2011122621/07A patent/RU2506658C2/ru not_active IP Right Cessation
- 2009-11-06 CN CN200980144243.XA patent/CN102203881B/zh not_active Expired - Fee Related
- 2009-11-06 WO PCT/EP2009/064736 patent/WO2010052298A1/fr active Application Filing
- 2009-11-06 US US13/126,159 patent/US8708258B2/en not_active Expired - Fee Related
-
2011
- 2011-04-28 ZA ZA2011/03110A patent/ZA201103110B/en unknown
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS56104294A (en) * | 1980-01-09 | 1981-08-19 | Atomic Energy Authority Uk | Method of recovering |
JPS604890A (ja) * | 1983-06-23 | 1985-01-11 | 株式会社日立製作所 | セラミツク核燃料再処理における前処理方法 |
JPS6118895A (ja) * | 1984-07-05 | 1986-01-27 | 株式会社神戸製鋼所 | 使用済核燃料棒の分解方法 |
JPS61119330A (ja) * | 1984-11-14 | 1986-06-06 | テーハー、キーゼルリング、ウント、アルブレヒト、ゲゼルシヤフト、ミツト、ベシユレンクテル、ハフツング、ウント、コンパニ | 傾斜ローラくせ取り機 |
JPS63182599A (ja) * | 1987-01-26 | 1988-07-27 | 株式会社神戸製鋼所 | 使用済燃料の脱被覆方法 |
JP2005043331A (ja) * | 2003-07-09 | 2005-02-17 | Japan Nuclear Cycle Development Inst States Of Projects | 使用済核燃料の脱被覆方法及び脱被覆装置 |
Also Published As
Publication number | Publication date |
---|---|
FR2938110A1 (fr) | 2010-05-07 |
EP2345041B1 (fr) | 2014-06-18 |
US8708258B2 (en) | 2014-04-29 |
CN102203881A (zh) | 2011-09-28 |
ZA201103110B (en) | 2011-12-28 |
EP2345041A1 (fr) | 2011-07-20 |
CN102203881B (zh) | 2014-11-05 |
WO2010052298A1 (fr) | 2010-05-14 |
RU2506658C2 (ru) | 2014-02-10 |
FR2938110B1 (fr) | 2013-02-15 |
JP5548689B2 (ja) | 2014-07-16 |
RU2011122621A (ru) | 2012-12-20 |
US20110204167A1 (en) | 2011-08-25 |
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