JP2987070B2 - Method of cutting the structure inside the reactor pressure vessel - Google Patents
Method of cutting the structure inside the reactor pressure vesselInfo
- Publication number
- JP2987070B2 JP2987070B2 JP7042992A JP4299295A JP2987070B2 JP 2987070 B2 JP2987070 B2 JP 2987070B2 JP 7042992 A JP7042992 A JP 7042992A JP 4299295 A JP4299295 A JP 4299295A JP 2987070 B2 JP2987070 B2 JP 2987070B2
- Authority
- JP
- Japan
- Prior art keywords
- cutting
- reactor
- cut
- shroud
- pressure vessel
- 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.)
- Expired - Fee Related
Links
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
- Arc Welding In General (AREA)
- Working Measures On Existing Buildindgs (AREA)
Description
【０００１】[0001]
【産業上の利用分野】本発明は、原子力発電プラント等
に採用されている原子炉の炉内構造物の切断方法に関す
る。The present invention relates to a method for cutting reactor internal component of the reactor which is employed in the nuclear power plant or the like.
【０００２】[0002]
【従来の技術】原子力発電プラント等において、原子炉
炉内の構造物、例えばシュラウド、炉心支持板や上部格
子板などを新規の構造物に取替える場合、あるいは原子
力発電プラントの廃止措置（廃炉）時に炉内構造物を廃
棄処分する場合、それらの構造物をそのまま炉外に運び
出すことは大きさの関係から難しく、一般には炉内で切
断しある程度の大きさにして運び出すことが行なわれて
いる。 And have your BACKGROUND ART nuclear power plant or the like, the structure of the nuclear reactor furnace, for example a shroud, when replacing the like core support plate and the top guide to the new structure, or decommissioning of a nuclear power plant (decommissioning) during furnace construction waste disposed of if, its possible to carry out these structures directly out of the furnace is difficult from the size relationship, generally cut in a furnace in the certain size Carrying out is taking place.
【０００３】また、この構造物の撤去にはもう一つの大
きな問題がある。すなわち、作業者の被ばくの問題であ
る。このように限られた炉心内の空間で、作業者が被ば
くすることなく切断およびその運搬を行うことは非常に
難しく、これら炉心内構造物の撤去には多くの時間また
神経が費やされる。There is another major problem with the removal of this structure. That is, it is a problem of worker exposure. In such a limited space in the core, it is very difficult for an operator to perform cutting and transportation without exposure, and removal of these core structures requires much time and nerves.
【０００４】従来の炉内構造物の切断方法またその装置
としては、原子炉内部構造物の取替工法として、例えば
特開昭６３−３６１９５号公報にも開示されているよう
に、遠隔操作式切断装置による切断方法がある。この遠
隔操作式切断装置による原子炉内部のシュラウド、上部
格子板、炉心支持板の取替え工法としては、据付け後の
機器の信頼性、作業者の被ばく低減の観点より極めて有
望な取替え工法と言える。[0004] A conventional method for cutting the internal structure of the reactor and its apparatus include a remote operation type as disclosed in, for example, JP-A-63-36195 as a method for replacing the internal structure of the reactor. There is a cutting method using a cutting device. The method of replacing the shroud, upper lattice plate, and core support plate inside the reactor by this remote-controlled cutting device can be said to be a very promising replacement method from the viewpoint of reliability of equipment after installation and reduction of exposure of workers.
【０００５】[0005]
【発明が解決しようとする課題】しかし、この従来の炉
内構造物の取替法では、切断法については工程短縮およ
び廃棄物の処理の観点で改善の余地を残している。たと
えば、前述した取替法では、シュラウドをシュラウドサ
ポートプレートと炉心支持板間で切断したあと、炉外に
搬出するようにしている。原子力発電プラント運転後に
シュラウド、炉心支持板および上部格子板等の機器を廃
棄処分とする場合、これらの機器は放射化されており遮
蔽容器等に詰め込み炉外に搬出することになるが、シュ
ラウドをシュラウドサポートと炉心支持板間で切断し遮
蔽容器に詰め込み炉外に搬出する場合、切断したシュラ
ウドを一体で詰め込む大型の遮蔽容器が必要となり、原
子炉建屋の寸法制約および建屋床の許容重量の問題があ
り、大型遮蔽容器を使用したシュラウドの一体搬出はシ
ュラウドの切断回数を最小にするという利点はあるもの
の遮蔽容器取扱上で工夫を要する。However, in this conventional method for replacing the furnace internals, there is room for improvement in the cutting method from the viewpoint of shortening the process and treating waste. For example, in the replacement method described above, the shroud is cut between the shroud support plate and the core support plate, and then is carried out of the furnace. When disposing of equipment such as shroud, core support plate and upper lattice plate after nuclear power plant operation, these equipments are activated and packed in shielded containers, etc., and carried out of the furnace. When cutting between the shroud support and the core support plate and packing it in a shielding vessel and carrying it out of the furnace, a large shielding vessel is needed to pack the cut shroud together.This causes problems with the dimensional restrictions of the reactor building and the allowable weight of the building floor. Although there is an advantage that the unloading of the shroud using the large-sized shielding container minimizes the number of times the shroud is cut, a device is required in handling the shielding container.
【０００６】本発明の目的は、炉内構造物の切断作業に
要する時間を短縮でき、さらに切断に従事する作業員の
被ばく低減も図れる原子炉圧力容器内構造物の切断方法
を提供することにある。SUMMARY OF THE INVENTION It is an object of the present invention to reduce the time required for cutting the furnace internals , and to reduce the time required for the workers engaged in the cutting.
And to provide a method for cutting a dose reduction also attained the reactor pressure vessel internals.
【０００７】[0007]
【課題を解決するための手段】前記目的を達成するため
の第１の発明の特徴は、原子炉圧力容器および原子炉ウ
ェルに水を満たした状態で、前記原子炉圧力容器内にお
いて炉内構造物を切断し、該切断された炉内構造物を前
記原子炉ウェルに移動し、該原子炉ウェル内において前
記切断された炉内構造物を更に切断する。 [MEANS FOR SOLVING THE PROBLEMS] To achieve the above object
The first aspect of the present invention is a reactor pressure vessel and a reactor
Fill the reactor with water and place it in the reactor pressure vessel.
To cut the furnace internal structure, and
To the reactor well and
The cut furnace internals are further cut.
【０００８】第２の発明の特徴は、第１の発明におい
て、前記原子炉圧力容器内における切断作業と前記原子
炉ウェル内における切断作業とを並行して行う。 [0008] The feature of the second invention is the first invention.
The cutting operation in the reactor pressure vessel and the
The cutting operation in the furnace well is performed in parallel.
【０００９】第３の発明の特徴は、第１または第２の発
明において、前記原子炉ウェル内で切断された炉内構造
物を、前記原子炉ウェル内において容器に入れる。 [0009] A feature of the third invention is that the first or second invention is provided.
, A reactor internal structure cut in the reactor well
An object is placed in a container in the reactor well.
【００１０】[0010]
【作用】第１の発明によれば、原子炉圧力容器および原
子炉ウェルで炉内構造物の切断作業を行うことにより、
原子炉圧力容器内だけで切断作業を実施する場合に比べ
切断作業スペースが確保できる。また、１次切断作業を
原子炉圧力容器内、２次切断作業を原子炉ウェル内で実
施することにより、原子炉圧力容器および原子炉ウェル
での同時期の作業が可能となるので、切断作業時間の短
縮が図れる。更に、水中における短時間の切断作業であ
ることから、切断に従事する作業員の被ばく低減も図る
ことができる。 According to the first aspect of the present invention , the reactor internal structure is cut in the reactor pressure vessel and the reactor well by performing
Cutting working space compared to the case of performing the cutting operation in only the reactor pressure vessel Ru secured. In addition, by performing the primary cutting work in the reactor pressure vessel and the secondary cutting work in the reactor well, the work in the reactor pressure vessel and the reactor well can be performed at the same time. Time can be reduced. Furthermore, short cutting work in water
To reduce the exposure of workers engaged in cutting
be able to.
【００１１】第２の発明によれば、１次切断作業（原子
炉圧力容器内の切断作業）及び２次切断作業（原子炉ウ
ェル内の切断作業）を並行して実施することにより、切
断作業時間の短縮及び作業員の被爆低減をより効率的に
図れる。 第３の発明によれば、ウェル内における切断さ
れた炉内構造物の容器への搬入と、１次切断作業も並行
して実施できるので、これも作業員の被曝低減に寄与す
る。 According to the second invention, the primary cutting operation (atomic
Cutting work in the reactor pressure vessel) and secondary cutting work (reactor c
Cutting work in the well) in parallel
Shortening the cutting time and reducing the exposure of workers more efficiently
I can do it. According to the third invention, the cut in the well is
Of the furnace internals into the vessel and primary cutting
This also contributes to reducing the exposure of workers.
You.
【００１２】[0012]
【実施例】以下図示した実施例に基づいて本発明を詳細
に説明する。図１におよび図２には、その炉内構造物の
切断方法および撤去方法が示されている。中央部には原
子炉圧力容器１が配置されており、この原子炉圧力容器
内の構造物、例えばシュラウド２を切断し撤去するわけ
であるが、この切断撤去に際して、まず原子炉圧力容器
１とその上方部に形成されている原子炉ウェル３に炉水
を満し、この状態でシュラウド２の切断作業が行われ
る。DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention will be described below in detail with reference to the illustrated embodiments. 1 and 2 show a method for cutting and removing the furnace internals. A reactor pressure vessel 1 is disposed in the center, and the structure inside the reactor pressure vessel, for example, the shroud 2 is cut and removed. The reactor well 3 formed in the upper part is filled with reactor water, and the cutting operation of the shroud 2 is performed in this state.
【００１３】シュラウド２の１次切断は、燃料交換台車
レール１４上に設置された移動台車１１、伸縮管マスト
旋回機構９、マスト伸縮機構１０、伸縮管マスト８、開
閉脚１２、トーチ１３、プラズマ発生装置４、制御盤
５、ケーブル６、７より構成される１次切断装置により
行われ、シュラウド２はリング状に切断される。[0013] The primary cutting of the shroud 2 is performed by moving the carriage 11 installed on the fuel exchange truck rail 14, the telescopic tube mast turning mechanism 9, the mast telescopic mechanism 10, the telescopic tube mast 8, the opening and closing leg 12, the torch 13, the plasma, and the like. The shroud 2 is cut into a ring shape by a primary cutting device including a generator 4, a control panel 5, and cables 6, 7.
【００１４】リング状に切断されたシュラウド切断片２
５は、移動台車１１上に設置された伸縮管掴み治具１
６、掴み治具伸縮機構１５、Ｘ方向移動機構４０より構
成される伸縮管方式の切断片移動装置により原子炉ウェ
ル３に設置された１次切断片保持架台２６まで移送さ
れ、そして１次切断片保持架台２６に固定される。次い
で、このリング状のシュラウド切断片２５は、サービス
フロアに設置された旋回機構１９、多関節アーム２０、
伸縮管マスト２３、トーチ２４、プラズマ発生装置１
７、制御盤１８、ケーブル２１、２２より構成される２
次切断装置によりさらに細かく切断される。Shroud cut piece 2 cut into a ring
5 is a telescopic tube gripping jig 1 installed on a movable carriage 11
6. The telescopic tube-type cutting piece moving device including the gripping jig expansion / contraction mechanism 15 and the X-direction moving mechanism 40 is transferred to the primary cutting piece holding gantry 26 installed in the reactor well 3, and then primary cut. It is fixed to the one-side holding base 26. Next, the ring-shaped shroud cutting piece 25 is attached to the turning mechanism 19, the multi-joint arm 20,
Telescopic tube mast 23, torch 24, plasma generator 1
7, composed of a control panel 18, cables 21 and 22
Next, it is further finely cut by the cutting device.
【００１５】前記２次切断装置により細断された切断片
２９は、浮子兼移動装置２８、掴み治具３０より構成さ
れる浮子方式切断片移動装置により原子炉ウェル３に設
置された切断片保管箱２７に詰め込まれる。この切断片
保管箱２７は、原子炉建屋の天井クレーンによりサービ
スフロアに移動されその後原子炉建屋外に搬出、保管さ
れる。The cut pieces 29 cut by the secondary cutting device are stored in the reactor well 3 by a float type cut piece moving device comprising a floater / moving device 28 and a gripping jig 30. Packed in box 27. The cut piece storage box 27, nuclear reactors are moved to the floors by an overhead crane of the building then the reactor building outside the discharge is stored.
【００１６】このようにすると、シュラウド２の１次切
断と２次切断は並行して作業を進めることが出来、しか
も浮子方式切断片移動装置は原子炉ウェル内を自在に移
動することが可能であるので、切断片２９の切断片保管
箱２７への搬入とシュラウド２の１次切断も並行して作
業を進めることが可能である。In this way, the primary cutting and the secondary cutting of the shroud 2 can proceed in parallel, and the floating piece moving device can move freely in the reactor well. Therefore, the work of loading the cut pieces 29 into the cut piece storage box 27 and the primary cutting of the shroud 2 can be performed in parallel.
【００１７】図２には、１次切断装置の降下方式にワイ
ヤロープ３２、ワイヤロープ巻取り機構３１、３９を採
用し、開閉脚３７、トーチ３８を水圧シリンダ３５、シ
リンダサポート３４、固定パッド３６によりシュラウド
２の１次切断部近傍で固定する１次切断装置の例が示さ
れている。In FIG. 2, a wire rope 32 and wire rope take-up mechanisms 31 and 39 are employed in the descending method of the primary cutting device, and the opening / closing leg 37 and the torch 38 are connected to a hydraulic cylinder 35, a cylinder support 34, and a fixing pad 36. 1 shows an example of a primary cutting device that is fixed in the vicinity of a primary cutting portion of the shroud 2.
【００１８】開閉脚３７、およびトーチ３８の旋回は旋
回機構４１により行い、切断速度等の条件は制御装置５
よりケーブル７、ケーブル３３を介し旋回機構４１に伝
達される。１次切断装置以外は図１に示す例と同様であ
る。図１、２共切断にプラズマ方式を採用した例を示し
たがウォータージェット、レーザについてもプラズマ方
式と同様にシュラウド２の切断を行うことが可能であ
る。The swing of the open / close legs 37 and the torch 38 is performed by a swing mechanism 41.
The rotation is transmitted to the turning mechanism 41 via the cable 7 and the cable 33. Other than the primary cutting device, it is the same as the example shown in FIG. FIGS. 1 and 2 show an example in which a plasma method is used for cutting, but it is also possible to cut the shroud 2 using a water jet or laser in the same manner as in the plasma method.
【００１９】また、図１、２共に炉内構造物としてシュ
ラウド２を例にとり１次切断、２次切断のシステム構成
を示したもので、本例に示す考え方により切断作業の短
縮、作業者の被ばく低減が図れる。また、図１、２の例
で複数の２次切断装置による切断を行うことも可能で有
る。FIGS. 1 and 2 show a system configuration for primary cutting and secondary cutting using a shroud 2 as an example of a furnace internal structure. Exposure can be reduced. In addition, it is also possible to perform cutting by a plurality of secondary cutting devices in the examples of FIGS.
【００２０】図３にシュラウド２の１次切断位置の例を
示す。なお、三角は切断位置を示している。シュラウド
２は、上部フランジ４２、上部胴４３、中間フランジ４
４、中間胴４５、下部フランジ４６、下部胴４７より構
成されている。この切断例は上部フランジ４２を上部胴
４３より切断し、次に上部胴４３を中間フランジ４４よ
り切断、次に中間フランジ４４を中間胴４５より切断す
る。中間胴４５は４分割に切断し、その後下部フランジ
４６の切断を行い、続いて下部胴４７の切断を行う。下
部胴は２分割に切断し最後にシュラウドサポートシリン
ダ４８との切断を行う。FIG. 3 shows an example of a primary cutting position of the shroud 2. Note that a triangle indicates a cutting position. The shroud 2 includes an upper flange 42, an upper trunk 43, and an intermediate flange 4.
4, an intermediate body 45, a lower flange 46, and a lower body 47. In this cutting example, the upper flange 42 is cut from the upper body 43, then the upper body 43 is cut from the intermediate flange 44, and then the intermediate flange 44 is cut from the intermediate body 45. The intermediate body 45 is cut into four parts, then the lower flange 46 is cut, and then the lower body 47 is cut. The lower body is cut into two parts and finally cut with the shroud support cylinder 48.
【００２１】以上がシュラウド２の１次切断で１次切断
装置を使用し原子炉圧力容器１内で切断作業を行う。図
３に示す様な切断を行うことでリング状の各切断片の高
さを実用上差し支えのない大きさ，すなわち１ｍ以内に
することができる。The above is the primary cutting of the shroud 2 and the cutting operation is performed in the reactor pressure vessel 1 using the primary cutting device. By performing the cutting as shown in FIG. 3, the height of each of the ring-shaped cut pieces can be reduced to a size that is practically acceptable, that is, within 1 m.
【００２２】図４〜図９にはシュラウド２の２次切断例
が示されている。図７中の点線４９、５０、５１は中間
フランジ４４（図６）における中間フランジの１次切断
線を、また図９の点線５２は下部胴４７における下部胴
の１次切断線を示している。上部フランジ４２（図
４）、上部胴４３（図５）、４分割の中間フランジ４４
（図６）、中間胴４５（図７）、下部フランジ４６（図
８）および２分割の下部胴４７（図９）は、それぞれ円
周１２分割とすることでそれぞれの切断片は１ｍ×１ｍ
以内にすることができる。以上がシュラウド２の２次切
断で２次切断装置を使用し原子炉ウェル３内で作業を行
う。FIGS. 4 to 9 show examples of secondary cutting of the shroud 2. Dotted lines 49, 50 and 51 in FIG. 7 indicate primary cutting lines of the intermediate flange in the intermediate flange 44 (FIG. 6), and dotted lines 52 in FIG. . Upper flange 42 (FIG. 4), upper body 43 (FIG. 5), and four-part intermediate flange 44
(FIG. 6), the intermediate body 45 (FIG. 7), the lower flange 46 (FIG. 8), and the two-part lower body 47 (FIG. 9) are each divided into twelve circumferences so that each cut piece is 1 mx 1 m
Within. As described above, the secondary cutting of the shroud 2 is performed in the reactor well 3 using the secondary cutting device.
【００２３】図１０には、細断された切断片保管する切
断片保管箱２７の例が示されている。この例は鉛製の厚
板容器で遮蔽を兼用する例である。鉛製とすることで鉄
製の容器の場合に比し板厚を約２／３にすることが出
来、原子炉ウェル３に設置する場合のスペース確保上有
利と言える。FIG. 10 shows an example of a cut piece storage box 27 for storing cut pieces. This example is an example in which a thick plate container made of lead also serves as a shield. By using lead, the plate thickness can be reduced to about 2/3 as compared with the case of an iron container, which can be said to be advantageous in securing a space when installed in the reactor well 3.
【００２４】以上説明してきたようにこの切断方法によ
り、炉内構造物の切断作業を１次切断、２次切断並行し
て進めることができるので、比較的短時間にかつ円滑に
進められ、また、短時間の切断作業であることから切断
作業に従事する作業員の被ばく低減も図れる。また、シ
ュラウド等炉内構造物の切断片は細断されることから、
炉外への搬出が切断片を詰め込む遮蔽容器も含め比較的
容易となる。As described above, according to this cutting method, the cutting operation of the furnace internal structure can be performed in parallel with the primary cutting and the secondary cutting, so that the cutting can be performed smoothly in a relatively short time. Since the cutting operation is performed in a short time, it is possible to reduce the exposure of a worker engaged in the cutting operation. In addition, since the cut pieces of the furnace internals such as shrouds are shredded,
It is relatively easy to carry it out of the furnace, including the shielding container that packs the cut pieces.
【００２５】[0025]
【発明の効果】本発明によれば、炉内構造物の切断作業
を、原子炉圧力容器内と原子炉ウェル内の２段階に分け
て、並行して行えるので、切断作業は短時間にかつ円滑
に実施できる。さらに短時間の切断作業であることから
切断に従事する作業員の被ばく低減を図ることができ
る。According to the present invention, a cutting operation of a furnace internal structure is performed.
Is divided into two stages in the reactor pressure vessel and the reactor well .
Therefore, the cutting operation can be performed in a short time and smoothly . Further, since the cutting operation is performed in a short time, it is possible to reduce the exposure of the worker engaged in the cutting.
【図１】本発明の原子炉圧力容器内構造物の撤去方法の
一実施例を説明するための原子炉圧力容器周辺を示す縦
断側面図である。FIG. 1 is a longitudinal sectional side view showing the vicinity of a reactor pressure vessel for explaining one embodiment of a method for removing an internal structure of a reactor pressure vessel of the present invention.
【図２】本発明の原子炉圧力容器内構造物の撤去方法の
他の実施例を説明するための原子炉圧力容器周辺を示す
縦断側面図である。FIG. 2 is a vertical sectional side view showing the vicinity of a reactor pressure vessel for explaining another embodiment of the method for removing the internal structure of the reactor pressure vessel of the present invention.
【図３】本発明の切断方法によるシュラウド１次切断例
を示す縦断側面図である。FIG. 3 is a longitudinal sectional side view showing an example of primary shroud cutting by the cutting method of the present invention.
【図４】本発明の切断方法によるシュラウド１次切断例
を示す縦断側面図である。FIG. 4 is a longitudinal sectional side view showing an example of primary shroud cutting by the cutting method of the present invention.
【図５】本発明の切断方法によるシュラウド１次切断例
を示す縦断側面図である。FIG. 5 is a longitudinal side view showing an example of primary shroud cutting by the cutting method of the present invention.
【図６】本発明の切断方法によるシュラウド１次切断例
を示す縦断側面図である。FIG. 6 is a longitudinal sectional side view showing an example of primary shroud cutting by the cutting method of the present invention.
【図７】本発明の切断方法によるシュラウド１次切断例
を示す縦断側面図である。FIG. 7 is a longitudinal sectional side view showing an example of primary shroud cutting by the cutting method of the present invention.
【図８】本発明の切断方法によるシュラウド１次切断例
を示す縦断側面図である。FIG. 8 is a longitudinal sectional side view showing an example of primary shroud cutting by the cutting method of the present invention.
【図９】本発明の切断方法によるシュラウド１次切断例
を示す縦断側面図である。FIG. 9 is a vertical sectional side view showing an example of primary shroud cutting by the cutting method of the present invention.
【図１０】本発明に用いられる切断片保管箱の一実施例
を示す斜視図である。FIG. 10 is a perspective view showing one embodiment of a cut piece storage box used in the present invention.
１…原子炉圧力容器、２…シュラウド、３…原子炉ウェ
ル、４…プラズマ発生装置、５…制御盤、６…ケーブ
ル、７…ケーブル、８…伸縮管マスト、９…伸縮管マス
ト旋回機構、１０…マスト伸縮機構、１１…移動台車、
１２…開閉脚、１３…トーチ、１４…燃料交換台車レー
ル、１５…掴み治具伸縮機構、１６…伸縮管掴み治具、
１７…プラズマ発生装置、１８…制御盤、１９…旋回機
構、２０…多関節アーム、２１…ケーブル、２２…ケー
ブル、２３…伸縮管マスト、２４…トーチ、２５…シュ
ラウド切断片、２６…１次切断片保持架台、２７…切断
片保管箱、２８…浮子兼移動装置、２９…切断片、３０
…掴み治具、３１…ワイヤロープ巻取り機構、３２…ワ
イヤロープ、３３…ケーブル、３４…シリンダサポー
ト、３５…水圧シリンダ、３６…固定パッド、３７…開
閉脚、３８…トーチ、３９…ワイヤロープ巻取り機構、
４０…Ｘ方向移動機構、４１…旋回機構、４２…上部フ
ランジ、４３…上部胴、４４…中間フランジ、４５…中
間胴、４６…下部フランジ、４７…下部胴、４８…シュ
ラウドサポートシリンダ、４９…中間フランジの１次切
断線、５０…中間フランジの１次切断線、５１…中間フ
ランジの１次切断線、５２…下部胴の１次切断線。DESCRIPTION OF SYMBOLS 1 ... Reactor pressure vessel, 2 ... Shroud, 3 ... Reactor well, 4 ... Plasma generator, 5 ... Control panel, 6 ... Cable, 7 ... Cable, 8 ... Telescopic tube mast, 9 ... Telescopic tube mast turning mechanism, 10 ... mast extension mechanism, 11 ... moving trolley,
12: open / close legs, 13: torch, 14: refueling truck rail, 15: gripping jig telescopic mechanism, 16: telescopic tube gripping jig,
Reference Signs List 17 plasma generator, 18 control panel, 19 turning mechanism, 20 articulated arm, 21 cable, 22 cable, 23 telescopic tube mast, 24 torch, 25 shroud cut piece, 26 primary Cut piece holding frame, 27: Cut piece storage box, 28: Floating and moving device, 29: Cut piece, 30
... Grip jig, 31 ... Wire rope winding mechanism, 32 ... Wire rope, 33 ... Cable, 34 ... Cylinder support, 35 ... Hydraulic cylinder, 36 ... Fixed pad, 37 ... Opening / closing leg, 38 ... Torch, 39 ... Wire rope Winding mechanism,
Reference numeral 40: X-direction moving mechanism, 41: turning mechanism, 42: upper flange, 43: upper trunk, 44: intermediate flange, 45: intermediate trunk, 46: lower flange, 47: lower trunk, 48: shroud support cylinder, 49 ... Primary cutting line of the intermediate flange, 50: Primary cutting line of the intermediate flange, 51: Primary cutting line of the intermediate flange, 52: Primary cutting line of the lower trunk.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 菊池 孝司 茨城県日立市幸町三丁目１番１号 株式 会社日立製作所日立工場内 (72)発明者 千葉 功男 茨城県日立市幸町三丁目１番１号 株式 会社日立製作所日立工場内 (72)発明者 木原 純秀 茨城県日立市幸町三丁目１番１号 株式 会社日立製作所日立工場内 (56)参考文献 特開 昭63−36195（ＪＰ，Ａ) 特開 平３−18797（ＪＰ，Ａ) 特開 平４−290998（ＪＰ，Ａ) (58)調査した分野(Int.Cl.6，ＤＢ名) G21C 19/02 G21F 9/30 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Koji Kikuchi, Inventor Hitachi 1-1, Hitachi City, Ibaraki Prefecture Inside the Hitachi Works, Ltd. (72) Inventor Isao Chiba 3-1-1, Sachimachi, Hitachi City, Ibaraki Prefecture No. 1 Inside Hitachi, Ltd. Hitachi Plant (72) Inventor Junhide Kihara 3-1-1 Sachimachi, Hitachi-shi, Ibaraki Pref. Inside Hitachi Plant, Hitachi, Ltd. (56) References JP-A-63-36195 (JP) JP-A-3-18797 (JP, A) JP-A-4-290998 (JP, A) (58) Fields investigated (Int. Cl. 6 , DB name) G21C 19/02 G21F 9/30
Claims (3)
満たした状態で、前記原子炉圧力容器内において炉内構
造物を切断し、該切断された炉内構造物を前記原子炉ウ
ェルに移動し、該原子炉ウェル内において前記切断され
た炉内構造物を更に切断することを特徴とする原子炉圧
力容器内構造物の切断方法。 1. Water is supplied to a reactor pressure vessel and a reactor well.
In the filled state, the reactor internal
The reactor structure is cut and the cut reactor internal structure is
Into the reactor well and the cut in the reactor well
Reactor pressure characterized by further cutting the internal reactor structure
How to cut the structure inside the power container.
における切断作業と前記原子炉ウェル内における切断作
業とを並行して行うことを特徴とする原子炉圧力容器内
構造物の切断方法。 2. The reactor pressure vessel according to claim 1, wherein
Work and cutting work in the reactor well
Inside the reactor pressure vessel, characterized in that the operation is performed in parallel
How to cut the structure.
ェル内で切断された炉内構造物を、前記原子炉ウェル内
において容器に入れることを特徴とする原子炉圧力容器
内構造物の切断方法。 3. The reactor according to claim 1, wherein
The reactor internal structure cut in the well is placed in the reactor well.
Reactor pressure vessel characterized in that it is placed in a vessel at
How to cut internal structures.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7042992A JP2987070B2 (en) | 1995-03-02 | 1995-03-02 | Method of cutting the structure inside the reactor pressure vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7042992A JP2987070B2 (en) | 1995-03-02 | 1995-03-02 | Method of cutting the structure inside the reactor pressure vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH08240693A JPH08240693A (en) | 1996-09-17 |
| JP2987070B2 true JP2987070B2 (en) | 1999-12-06 |
Family
ID=12651531
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP7042992A Expired - Fee Related JP2987070B2 (en) | 1995-03-02 | 1995-03-02 | Method of cutting the structure inside the reactor pressure vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2987070B2 (en) |
Families Citing this family (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4177964B2 (en) * | 1999-03-31 | 2008-11-05 | 日立Ｇｅニュークリア・エナジー株式会社 | How to carry out reactor internals |
| JP4276808B2 (en) * | 1999-09-29 | 2009-06-10 | 日立Ｇｅニュークリア・エナジー株式会社 | Equipment for carrying out nuclear power plant equipment |
| JP4088796B2 (en) * | 2004-07-29 | 2008-05-21 | 株式会社日立プラントテクノロジー | Reactor pressure vessel dismantling method |
| DE102007033376B4 (en) * | 2007-07-18 | 2012-04-26 | Areva Np Gmbh | Process for dismantling a nuclear installation |
| JP4850214B2 (en) | 2008-06-30 | 2012-01-11 | 日立Ｇｅニュークリア・エナジー株式会社 | Carrying out the reactor internals |
| JP2014059185A (en) * | 2012-09-14 | 2014-04-03 | Mitsubishi Heavy Ind Ltd | Reactor vessel lid dismantlement method and disposal method |
| JP6352769B2 (en) * | 2014-10-21 | 2018-07-04 | 株式会社東芝 | Cutting device and cutting method |
| JP6440030B2 (en) * | 2015-03-04 | 2018-12-19 | 株式会社Ihi | Demolition collection method and dismantling collection equipment for in-furnace structures |
| JP6704231B2 (en) * | 2015-10-02 | 2020-06-03 | 三菱重工業株式会社 | Nuclear plant dismantling method |
| JP2017021046A (en) * | 2016-09-29 | 2017-01-26 | 三菱重工業株式会社 | Disassembly method and disposal method for reactor vessel lid |
| JP6224288B1 (en) * | 2017-08-01 | 2017-11-01 | 三菱重工業株式会社 | Dismantling method and disposal method of reactor vessel lid |
| KR102061287B1 (en) * | 2018-04-17 | 2019-12-31 | 한국수력원자력 주식회사 | Dismantling and decontamination system and method of biodegradable concrete of pwr type nuclear power plant |
| KR102080906B1 (en) * | 2018-07-06 | 2020-02-24 | 한국수력원자력 주식회사 | Reactor dismantling apparatus |
| KR102080909B1 (en) | 2018-07-06 | 2020-02-24 | 한국수력원자력 주식회사 | Reactor dismantling system |
| KR102192100B1 (en) * | 2019-02-14 | 2020-12-16 | 한국수력원자력 주식회사 | Method for decommissioning nuclear facilities in water |
| KR102566506B1 (en) * | 2021-04-05 | 2023-08-23 | 두산에너빌리티 주식회사 | Method and apparatus for dismantling reactor vessel |
| KR102662554B1 (en) * | 2021-11-09 | 2024-04-30 | 한국수력원자력 주식회사 | Underwater cutting system and method in reactor cavity |
| KR102487513B1 (en) * | 2022-05-11 | 2023-01-12 | 한전케이피에스 주식회사 | Method for dismantling reactor internals |
-
1995
- 1995-03-02 JP JP7042992A patent/JP2987070B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH08240693A (en) | 1996-09-17 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP2987070B2 (en) | Method of cutting the structure inside the reactor pressure vessel | |
| JP3663924B2 (en) | Method for handling reactor internal structure and apparatus used for the method | |
| JP3126254B2 (en) | Reactor containment | |
| JP4596739B2 (en) | A platform for maintaining a nuclear reactor and a nuclear reactor maintenance method using the platform | |
| WO2004078931A2 (en) | Autonomous cask translocation crane | |
| JP4177987B2 (en) | Reactor vessel handling | |
| JP2000206294A (en) | Method for bringing out large equipment | |
| JP2003215294A (en) | Method and facility for handling structure | |
| GB2139804A (en) | Machines for dismantling decommissioned nuclear reactors | |
| US4036687A (en) | Nuclear reactors | |
| JP4276808B2 (en) | Equipment for carrying out nuclear power plant equipment | |
| JP4055157B2 (en) | Reactor pressure vessel replacement method | |
| JP2002131483A (en) | Method for handling large structure | |
| JP7467250B2 (en) | Method and device for dismantling nuclear reactor equipment | |
| US6731715B2 (en) | Reactor vessel handling method | |
| JPH06102398A (en) | Disposal method for reactor pressure vessel and its system | |
| JPH1054896A (en) | Method handling method and device | |
| JP2000346993A (en) | Method for handling large structure in reactor building | |
| JP4177964B2 (en) | How to carry out reactor internals | |
| JP6301764B2 (en) | Method of unloading nuclear equipment, unloading device thereof, and method of retrieving fuel debris | |
| JP4055156B2 (en) | Reactor pressure vessel replacement method | |
| JP4096911B2 (en) | Reactor pressure vessel replacement method | |
| JP2017106818A (en) | Transport method of fuel assembly in fuel storage pool | |
| Shourot | Nuclear reactor diving.[Underwater repair of fuel handling system] | |
| US20050238130A1 (en) | Refueling work platform |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| S531 | Written request for registration of change of domicile |
Free format text: JAPANESE INTERMEDIATE CODE: R313531 |
|
| R350 | Written notification of registration of transfer |
Free format text: JAPANESE INTERMEDIATE CODE: R350 |
|
| S111 | Request for change of ownership or part of ownership |
Free format text: JAPANESE INTERMEDIATE CODE: R313111 |
|
| R371 | Transfer withdrawn |
Free format text: JAPANESE INTERMEDIATE CODE: R371 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20081001 Year of fee payment: 9 |
|
| S111 | Request for change of ownership or part of ownership |
Free format text: JAPANESE INTERMEDIATE CODE: R313111 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20081001 Year of fee payment: 9 |
|
| R350 | Written notification of registration of transfer |
Free format text: JAPANESE INTERMEDIATE CODE: R350 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20091001 Year of fee payment: 10 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20101001 Year of fee payment: 11 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20111001 Year of fee payment: 12 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20121001 Year of fee payment: 13 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20131001 Year of fee payment: 14 |
|
| LAPS | Cancellation because of no payment of annual fees |