EP0465283A1 - Verfahren und Vorrichtung zur Zerlegung eines bestrahlten Komponents eines Kernreaktors durch Bearbeitung seiner Wandung - Google Patents
Verfahren und Vorrichtung zur Zerlegung eines bestrahlten Komponents eines Kernreaktors durch Bearbeitung seiner Wandung Download PDFInfo
- Publication number
- EP0465283A1 EP0465283A1 EP91401547A EP91401547A EP0465283A1 EP 0465283 A1 EP0465283 A1 EP 0465283A1 EP 91401547 A EP91401547 A EP 91401547A EP 91401547 A EP91401547 A EP 91401547A EP 0465283 A1 EP0465283 A1 EP 0465283A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- support
- machining
- wall
- chips
- tubular
- 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.)
- Withdrawn
Links
- 238000003754 machining Methods 0.000 title claims abstract description 42
- 238000000034 method Methods 0.000 title claims description 15
- 238000003801 milling Methods 0.000 claims abstract description 17
- 230000015572 biosynthetic process Effects 0.000 claims abstract description 5
- 239000002245 particle Substances 0.000 claims description 15
- 239000000463 material Substances 0.000 claims description 10
- 238000011084 recovery Methods 0.000 claims description 4
- 230000007774 longterm Effects 0.000 claims description 2
- 230000000284 resting effect Effects 0.000 claims description 2
- 238000003860 storage Methods 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 10
- 230000000712 assembly Effects 0.000 description 4
- 238000000429 assembly Methods 0.000 description 4
- 230000008030 elimination Effects 0.000 description 3
- 238000003379 elimination reaction Methods 0.000 description 3
- 241000196324 Embryophyta Species 0.000 description 2
- 238000011109 contamination Methods 0.000 description 2
- 239000000498 cooling water Substances 0.000 description 2
- 238000005520 cutting process Methods 0.000 description 2
- 238000006073 displacement reaction Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 230000006698 induction Effects 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 235000016623 Fragaria vesca Nutrition 0.000 description 1
- 240000009088 Fragaria x ananassa Species 0.000 description 1
- 235000011363 Fragaria x ananassa Nutrition 0.000 description 1
- 238000005266 casting Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000012809 cooling fluid Substances 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000002923 metal particle Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 230000009182 swimming Effects 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
- G21F9/005—Decontamination of the surface of objects by ablation
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T409/00—Gear cutting, milling, or planing
- Y10T409/30—Milling
- Y10T409/303752—Process
- Y10T409/303808—Process including infeeding
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T409/00—Gear cutting, milling, or planing
- Y10T409/30—Milling
- Y10T409/304088—Milling with means to remove chip
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T409/00—Gear cutting, milling, or planing
- Y10T409/30—Milling
- Y10T409/306216—Randomly manipulated, work supported, or work following device
- Y10T409/306384—Randomly manipulated, work supported, or work following device with work supported guide means
- Y10T409/30644—Randomly manipulated, work supported, or work following device with work supported guide means to guide tool to move in arcuate path
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T82/00—Turning
- Y10T82/10—Process of turning
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T82/00—Turning
- Y10T82/25—Lathe
- Y10T82/2522—Portable
Definitions
- the invention relates to a method and a device for dismantling an irradiated component of a nuclear reactor and in particular of a vessel of a nuclear reactor cooled by pressurized water, by machining its wall with removal of shavings.
- Water-cooled nuclear reactors and in particular pressurized water nuclear reactors comprise a vessel which is intended to contain the core of the nuclear reactor and which is connected to the cooling circuit of the reactor in which the cooling water circulates.
- the wall of the reactor vessel which is in contact with the cooling fluid and exposed to the radiation emitted by the reactor core can be highly contaminated after a certain period of operation of the reactor.
- the dismantling of the conventional part of the power plant does not pose any particular problem but on the other hand, the dismantling of the part of the power station constituting the nuclear reactor proper poses problems difficult to solve, due to the radioactive emissions of the materials constituting the components of the reactor.
- the tank of water-cooled nuclear reactors which contains the fuel assemblies and which is in contact with the cooling water of the reactor during its operation is very highly contaminated, in the case of reactors reaching the end of their life .
- the reactor vessel In the case of pressurized water nuclear reactors currently in operation, the reactor vessel is in the form of a generally cylindrical body closed by domed bottoms, of large dimension and having a large wall thickness.
- the tank which has a very high mass is disposed inside a tank well formed in a concrete structure which also delimits one or more swimming pools located above the upper level of the tank.
- the tank which contains, in addition to the fuel assemblies, various internal structures is connected, by tubes, to pipes of the primary circuit of the reactor.
- the core assemblies and certain components of the internal structures can be disassembled and taken out of the tank, so as to ensure their evacuation and, possibly, their elimination, when the reactor is put out of service.
- the object of the invention is therefore to propose a method for dismantling an irradiated component of a nuclear reactor comprising at least one wall of tubular shape arranged with its axis in the vertical direction, this method making it possible to carry out in very good safety conditions and in a simple manner elimination by machining with removal of chips from the material of the wall of the component and evacuation of the chips obtained.
- the invention also relates to a device implementing the dismantling method according to the invention.
- the single figure is a vertical sectional view in elevation of the upper part of a vessel of a pressurized water nuclear reactor and of a device ensuring the dismantling of this tank by the process according to the invention.
- the vessel 1 of a pressurized water nuclear reactor which is constituted by a casing of tubular shape having a large wall thickness arranged with its vertical axis inside a well. tank formed in a concrete structure not shown.
- the tubular tank has, at its upper part, a flange 2 whose thickness is greater than the thickness of the wall of the tank in its current part.
- the flange 2 is intended to receive the tank cover ensuring a tight closure of the interior volume of the tank during the operation of the reactor.
- the tank 1 also comprises, in the vicinity of its upper part, pipes such as 3 allowing the connection of the tank to the pipes of the primary circuit.
- the primary circuit and the tank are cooled and the tank cover is removed, the reactor pool located above the tank being filled with water.
- the core assemblies are unloaded and evacuated as well as the internal equipment of the tank.
- the reactor pool is then drained as well as the tank which can nevertheless be partially filled with water during the implementation of dismantling.
- a dismantling device for implementing the method according to the invention is installed on the upper part of the tank 1, using from the central unit's polar bridge or by another suitable lifting and handling means.
- the device 4 comprises a tubular support 5 placed, in the service position, with its axis coinciding with the axis 6 of the tank 1.
- the arms such as 7a and 7b are machined internally in their axial direction to form actuator chambers in which rods 9 move carrying at their ends support pads 10 on the internal wall of the tank 1.
- the arms such as 7a and 7b secure and center the device 4 by clamping inside the tank, when the jack rods 9 are in their extracted position.
- each of the arms such as 7a and 7b is fixed a support device 12 making it possible to rest the whole of the device 4 on the annular upper surface of the tank 1, to ensure its maintenance, independently of the clamping ensured by the set of radial steering arms such as 7a and 7b.
- Each of the support devices 12 comprises an arm 13 pivotally mounted by means of a joint 14 with a horizontal axis, on the corresponding arm.
- the pivoting arm 13 comprises, at its end opposite to the articulation 14, a support piece 15 coming to rest on the annular upper surface of the tank 1, when the arm 13 is in its low position as shown in the left part of the figure, above the arm 7a.
- the position of the support surface 15 in the direction of an axis 17 perpendicular to this support surface can be adjusted by a compensation device 16 whose operation will be explained in the following text.
- An actuating cylinder 18 of the arm 13 is articulated on the external surface of the tubular support 5.
- the rod 19 of the cylinder 18 is connected, also articulated, to the arm 13.
- the axes of articulation of the jack 18 and of the rod 19 are placed in a horizontal direction.
- the tubular support 5 carries, in the vicinity of its upper part, a rotary bearing 20 having as axis the axis 6 common to the support 5 and to the tank 1.
- the bearing 20, constituted in the form of a roller bearing, comprises a fixed internal barye integral with the support 5 and an external ring movable in rotation on which is fixed a support 24.
- a radial direction arm 25 is movably mounted inside the support 24, in a direction 26 corresponding to its longitudinal direction.
- a geared motor 27 ensuring the drive of a pinion-rack assembly mounted in the support 24 makes it possible to move the arm 25 in the direction 26, in one direction and in the other, as shown diagrammatically by the arrow 28.
- the arm 25 carries, at its end opposite to the support 24, a milling head 30 constituting the tool for removing by machining the irradiated material from the wall of the tank 1.
- the milling head 30 comprises a milling cutter 31 mounted at the end of a vertical steering spindle rotated by a motor 32.
- the support 5 carries at its upper end, above the bearing 20, a fixed toothed crown 34.
- a geared motor 35 fixed on the mobile external barye of the bearing 20, carries, at the end of its output shaft, a pinion drive 36 meshing with the fixed ring gear 34.
- the rotation of the gear motor 35 and the pinion 36 allows to drive the outer ring of the bearing 20, the support 24 and the milling head 30 in rotation about the axis 6 of the tank.
- the arms such as 7a and 7b carry, by means of flexible fixing devices 38, a collecting hopper 39 of frustoconical shape and comprising a peripheral seal 40 along its upper edge whose diameter is substantially equal to the inside diameter of the tank 1.
- the seal 40 ensures a tight connection between the upper external edge of the collecting hopper 39 and the internal surface of the tank 1.
- a conveyor 41 of vertical direction connected, at its lower part, to an extension 5a of the support 5, is mounted, in the vertical direction, inside the support 5, so as to open, at its upper part, into a conduit 42 of flared shape.
- the chips and particles 44 coming into contact with the internal surface of the hopper 39 are directed by gravity towards the bottom of the hopper, this movement of the chips and particles being facilitated by the presence of a vibrator 47 in contact with the external surface hopper 39.
- the chips and particles which collect at the lower central part of the hopper 39 are taken up by the conveyor 41 and transported inside the support 5, up to its upper part to be discharged onto a handling device or into a hopper allowing to feed an induction furnace ensuring the reflow of the chips and particles of irradiated material from the wall of the tank.
- the flared conduit 42 ensures complete recovery of the chips and particles at the top of the conveyor 41, some of these chips or particles being able to be projected outside their normal transport path, which would cause contamination of the milling device. by these particles of radioactive material.
- the device 4 To carry out a dismantling operation of a tank 1 of a pressurized water nuclear reactor, the device 4 is placed in its operating position on the upper part 2 of the tank constituted by the cover fixing flange.
- the support devices 12 whose arms 13 are placed in the low position come to rest by their support pieces 15 on the upper surface of the flange 2.
- the device is clamped and fixed by feeding the cylinders provided in the arms such as 7a and 7b.
- the pads 10 come into contact with the inner surface of the tank to ensure the clamping.
- the milling cutter 31 which is, at the start of operation, in a position of withdrawal towards the inside of the tank is rotated and the arm 25 is moved outwards, so that the milling cutter, the position of which is in height is adjusted by the compensation devices 16 of the support pieces 15 of the arms 13 can engage in the metal of the wall of the tank 1 to a thickness corresponding to the thickness of a machining pass.
- the movable outer ring of the bearing 20, the support 24, the arm 25 and the milling head 30 are rotated about the axis 6 of the tank, by feeding the gearmotor 35.
- the milling head 30 rotating around the axis 6 performs a machining pass on the annular upper surface of the tank.
- a detector makes it possible to control the corresponding jack 18, by means of a servovalve.
- the arm 13 is moved by pivoting to come into a raised position such as position 13 ′.
- the compensation device 16 moves the support piece 15 outward over a distance corresponding to the thickness of the pass.
- a detector controls the displacement of the jack 18 in the direction causing the arm 13 to fold down. , the support piece 15 coming into contact with the surface of the wall of the freshly machined tank. Position adjustment of the support piece 15 ensures perfect contacting of this support piece with the upper surface of the tank, when the pivoting arm 13 is folded down and held in position by the rod 19 of the jack 18 in its deployed position.
- the machining pass is carried out during a complete revolution of the milling head 30 around the axis 6 of the tank, the arms 13 of the support devices 12 being moved in their high position, at the time of passage strawberry at their level.
- the complete machining of the upper surface of the tank according to the thickness of a pass may require a radial displacement of the cutter and carrying out several machining passes.
- the milling head 30 When the upper part of the tank 1 has been machined to the thickness corresponding to a machining pass, the milling head 30 is returned to its initial position and the rods 9 of the jacks associated with the arms such as 7a and 7b are placed in their retracted position, so as to release the clamping pads 10 of the device 4 inside the tank.
- the device 4 rests on the support devices 12 whose maintenance in the low position is ensured by the jacks 18.
- the compensation devices 16 are then reset, so as to be able to make the adjustments, at the time of the passage of the cutter, during the next machining pass.
- the jacks associated with the arms such as 7a and 7b are actuated so as to clamp the device 4 inside the tank.
- the chips and particles formed by the cutter 31 are continuously recovered by the hopper 39 and the vertical conveyor 41, so as to be continuously introduced into an induction reflow oven.
- the dismantling of the tank is ensured by removing the metal from its wall, during successive milling passes.
- the tool change is carried out in a conventional manner thanks to a robotic auxiliary arm which supports the cutter on the milling head to introduce it into a barrel or a display and to proceed with the installation of a new cutter having a satisfactory cutting condition.
- the dismantling process and device according to the invention therefore make it possible to dismantle a nuclear reactor vessel completely automatically, so that the time required to carry out the machining is only of secondary importance.
- the recovered irradiated material can be easily shaped by reflow and by casting to form blocks of irradiated material whose mass and shape make it possible to facilitate long-term storage.
- This device can include a different machining machine from a milling head.
- the means for moving, holding and centering the machining machine may be different from those which have been described. These means may include any number of arms, greater than two, to ensure the clamping of the machine on the tubular wall.
- All the handling means allowing the recovery of the chips or particles and their transport to a melting or recovery device can also be different from those which have been described.
- the invention applies to the dismantling of any component of a nuclear reactor comprising at least one part of tubular shape arranged with its vertical axis.
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Food Science & Technology (AREA)
- Working Measures On Existing Buildindgs (AREA)
- Disintegrating Or Milling (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR9008118A FR2664084B1 (fr) | 1990-06-27 | 1990-06-27 | Procede et dispositif de demantelement d'un composant irradie d'un reacteur nucleaire par usinage de sa paroi. |
FR9008118 | 1990-06-27 |
Publications (1)
Publication Number | Publication Date |
---|---|
EP0465283A1 true EP0465283A1 (de) | 1992-01-08 |
Family
ID=9398081
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP91401547A Withdrawn EP0465283A1 (de) | 1990-06-27 | 1991-06-11 | Verfahren und Vorrichtung zur Zerlegung eines bestrahlten Komponents eines Kernreaktors durch Bearbeitung seiner Wandung |
Country Status (5)
Country | Link |
---|---|
US (1) | US5158739A (de) |
EP (1) | EP0465283A1 (de) |
CS (1) | CS192491A3 (de) |
FR (1) | FR2664084B1 (de) |
HU (1) | HU208589B (de) |
Families Citing this family (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5936863A (en) * | 1998-01-28 | 1999-08-10 | Lockheed Martin Idaho Technologies Company | Optimal segmentation and packaging process |
DE19821892C1 (de) * | 1998-05-15 | 1999-12-30 | Bbc Reaktor Gmbh | Einrichtung zum Trennen einer Blechabdeckung eines Lagergestells für Brennelemente |
DE19822588C1 (de) * | 1998-05-20 | 1999-11-11 | Bbc Reaktor Gmbh | Einrichtung zum Trennen einer Blechabdeckung eines Brennelementlagergestells |
FR2785713B1 (fr) * | 1998-11-10 | 2000-12-08 | Commissariat Energie Atomique | Systeme de commande d'unites de levage et de telemanipulation placees en enceinte confinee |
US6485109B2 (en) | 1999-05-28 | 2002-11-26 | Simpson Industries, Inc. | Knuckle hub assembly and method for making same |
US6708589B2 (en) | 1999-05-28 | 2004-03-23 | Metaldyne Machining & Assembly Company, Inc. | Brake rotor assembly and method for making same |
US20040046440A1 (en) * | 2001-12-14 | 2004-03-11 | Daniel Brinker | Knuckle hub assembly and method for making same |
US6212981B1 (en) * | 1999-05-28 | 2001-04-10 | Simpson Industries, Inc. | Knuckle hub fixture assembly and method of using |
US20080131046A1 (en) * | 2006-11-01 | 2008-06-05 | Weier Glenn R | Apparatus and method for manufacturing knuckle and bearing assembly |
JP5371394B2 (ja) * | 2008-11-27 | 2013-12-18 | 株式会社三恵シーアンドシー | チルト装置 |
WO2010096765A1 (en) * | 2009-02-20 | 2010-08-26 | Diversified Machine Inc. | Wheel assembly and method for making same |
KR101522169B1 (ko) * | 2013-09-03 | 2015-05-22 | 두산중공업 주식회사 | 원자로 용기의 코어 서포트 패드 가공방법 및 그 가공장치 |
JP6320113B2 (ja) * | 2014-03-27 | 2018-05-09 | 三菱重工業株式会社 | 弁、及び放射性廃棄物固化装置 |
KR101585502B1 (ko) * | 2014-04-14 | 2016-01-22 | 한국원자력연구원 | CAD Kernel을 이용한 절단공정 시뮬레이션 방법 및 그 시스템 |
KR102159782B1 (ko) * | 2019-03-08 | 2020-09-24 | 한국수력원자력 주식회사 | 원자력 시설의 복합 해체 방법 |
Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2554256A1 (de) * | 1975-12-03 | 1977-06-16 | Steinmueller Gmbh L & C | Verfahren zur entsorgung eines kernkraftwerkes |
US4813313A (en) * | 1985-11-25 | 1989-03-21 | Kabushiki Kaisha Kobe Seiko Sho | Apparatus for demolishing a reactor shield wall |
Family Cites Families (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2706432A (en) * | 1951-07-27 | 1955-04-19 | Giddings & Lewis | Chip conveyor for milling machine |
US3908491A (en) * | 1974-03-22 | 1975-09-30 | Multi Fab Inc | Flange facing and cutting tool |
US4594774A (en) * | 1984-03-27 | 1986-06-17 | United Kingdom Atomic Energy Authority | Machines for dismantling decommissioned nuclear reactors |
DE3440277C1 (de) * | 1984-11-03 | 1986-05-22 | Siempelkamp Gießerei GmbH & Co, 4150 Krefeld | Verfahren zum Einbringen von radioaktiven Abfaellen in einen Schmelzofen und Vorrichtung zur Durchfuehrung des Verfahrens |
JPS62249986A (ja) * | 1986-04-21 | 1987-10-30 | Hamari Yakuhin Kogyo Kk | ポルフイリン誘導体 |
DE3764402D1 (de) * | 1986-06-02 | 1990-09-27 | Siemens Ag | Verfahren und anordnung zur nasszerlegung radioaktiv kontaminierter oder aktivierter komponenten von kernreaktoranlagen. |
JPH06100777B2 (ja) * | 1986-09-30 | 1994-12-12 | 三田工業株式会社 | 光学部支持装置 |
US5001870A (en) * | 1987-10-05 | 1991-03-26 | Kajima Corporation | Method of cutting and disassembling cylindrical structure |
JPH01187499A (ja) * | 1988-01-21 | 1989-07-26 | Science & Tech Agency | 原子炉解体用ロボット |
-
1990
- 1990-06-27 FR FR9008118A patent/FR2664084B1/fr not_active Expired - Fee Related
-
1991
- 1991-06-11 EP EP91401547A patent/EP0465283A1/de not_active Withdrawn
- 1991-06-24 CS CS911924A patent/CS192491A3/cs unknown
- 1991-06-25 HU HU912120A patent/HU208589B/hu not_active IP Right Cessation
- 1991-06-26 US US07/721,415 patent/US5158739A/en not_active Expired - Fee Related
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2554256A1 (de) * | 1975-12-03 | 1977-06-16 | Steinmueller Gmbh L & C | Verfahren zur entsorgung eines kernkraftwerkes |
US4813313A (en) * | 1985-11-25 | 1989-03-21 | Kabushiki Kaisha Kobe Seiko Sho | Apparatus for demolishing a reactor shield wall |
Non-Patent Citations (3)
Title |
---|
PATENT ABSTRACTS OF JAPAN, vol. 13, no. 324 (P-903)[3672], 21 juillet 1989; & JP-A-62 249 986 (KAJIMA CORP.) 11-04-1989 * |
PATENT ABSTRACTS OF JAPAN, vol. 13, no. 475 (P-950)[3823], 27 octobre 1989; & JP-A-1 187 499 (SCIENCE & TECH. AGENCY) 26-07-1989 * |
PATENT ABSTRACTS OF JAPAN, vol. 14, no. 191 (P-1038)[4134], 19 avril 1990; & JP-A-63 184 733 (JAPAN ORGANO CO., LTD) 06-02-1990 * |
Also Published As
Publication number | Publication date |
---|---|
US5158739A (en) | 1992-10-27 |
FR2664084B1 (fr) | 1993-07-16 |
HU912120D0 (en) | 1991-12-30 |
CS192491A3 (en) | 1992-02-19 |
FR2664084A1 (fr) | 1992-01-03 |
HU208589B (en) | 1993-11-29 |
HUT59503A (en) | 1992-05-28 |
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