JPS58131592A - Method of capturing cladding in reactor pressure vessel - Google Patents

Method of capturing cladding in reactor pressure vessel

Info

Publication number
JPS58131592A
JPS58131592A JP57013750A JP1375082A JPS58131592A JP S58131592 A JPS58131592 A JP S58131592A JP 57013750 A JP57013750 A JP 57013750A JP 1375082 A JP1375082 A JP 1375082A JP S58131592 A JPS58131592 A JP S58131592A
Authority
JP
Japan
Prior art keywords
pressure vessel
reactor pressure
filter
reactor
flange
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
Application number
JP57013750A
Other languages
Japanese (ja)
Inventor
武 本間
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
SHISUTEMU MAINTENANCE KK
SYSTEM MAINTENANCE KK
Original Assignee
SHISUTEMU MAINTENANCE KK
SYSTEM MAINTENANCE KK
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by SHISUTEMU MAINTENANCE KK, SYSTEM MAINTENANCE KK filed Critical SHISUTEMU MAINTENANCE KK
Priority to JP57013750A priority Critical patent/JPS58131592A/en
Publication of JPS58131592A publication Critical patent/JPS58131592A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physical Or Chemical Processes And Apparatus (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 この発明は原子炉圧力容器内のクラッドの捕獲方法に関
する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for capturing crud within a nuclear reactor pressure vessel.

従来、原子炉圧力容器内には放射化されたクラッドが存
在し、放射線防護及び原子炉システムを維持して行く上
での阻害要因となっている。例えば、原子炉圧力容器よ
り核燃料を取シ出す際は高放射線量のための水中を移動
する必要があり、原子炉圧力容器上部の原子炉ウェルに
水を張る必要がある。この水張りは、原子炉圧力容器内
の水位性なうが、この時原子炉圧力容器内に存在するク
ラッドが、水位の上昇と共に原子炉ウェル内に浸入する
。このため核燃料の変換等が完了し、原子炉ウェル内の
水を除去した後、原子炉ウェル壁面にクラッドが付着残
留する。このクラッドは放射化しているので除染する必
要があるが、放射線雰囲気下の作業である為制約を受け
る。例えば原子炉圧力容器周囲・原子炉格納容器周囲に
あるペロ一部は挾隘で形状が複雑である丸め除染・洗浄
が困難であるし、原子力発電所の定期検査では、原子炉
ウェルの除染がクリチカル工程となっているので9作業
は円滑に実施する必要がある。このため、原子炉ウェル
の除染には多くの労力を要し。
Conventionally, activated crud exists within a nuclear reactor pressure vessel, which is an impediment to radiation protection and maintenance of the nuclear reactor system. For example, when removing nuclear fuel from a reactor pressure vessel, it is necessary to move through water due to the high radiation dose, and it is necessary to fill the reactor well above the reactor pressure vessel with water. This water filling is caused by the water level in the reactor pressure vessel, and at this time, crud existing in the reactor pressure vessel infiltrates into the reactor well as the water level rises. For this reason, after the conversion of nuclear fuel, etc. is completed and the water in the reactor well is removed, crud remains attached to the wall surface of the reactor well. Since this crud is radioactive, it must be decontaminated, but there are restrictions because the work is under a radiation atmosphere. For example, some of the wells around the reactor pressure vessel and reactor containment vessel are rounded and have a complicated shape, making decontamination and cleaning difficult. Since dyeing is a critical process, work 9 must be carried out smoothly. For this reason, decontamination of reactor wells requires a lot of effort.

放射線の被曝をしていた。He had been exposed to radiation.

本発明は、これ等の欠点を解消するために提供するもの
である。
The present invention is provided to eliminate these drawbacks.

本発明を図面について説明すると、第1図は容器1の上
部にある蓋2のノズル3,7ランジ4で構成された原子
炉圧力容器において、7ランジ4に濾過器5を取付ける
が、濾過器5の上部には出口管6を取付け、濾過器5の
下部には入口管7を取付け、入口管7の先端に7ランジ
8を固着し。
To explain the present invention with reference to the drawings, FIG. 1 shows a reactor pressure vessel composed of nozzles 3 and 7 flange 4 of a lid 2 at the upper part of the vessel 1, and a filter 5 is attached to the 7 flange 4. An outlet pipe 6 is attached to the upper part of the filter 5, an inlet pipe 7 is attached to the lower part of the filter 5, and a 7 flange 8 is fixed to the tip of the inlet pipe 7.

フランジ4とフランジ8はボルト及びナツトによシ接続
する。
Flange 4 and flange 8 are connected by bolts and nuts.

第2図は容器10フランジ9の上に覆い板1oを乗せる
。覆い板10には穴11があり、穴11の上には管12
を固着し、管12にはフランジ13が固着されている。
In FIG. 2, a cover plate 1o is placed on the flange 9 of the container 10. The cover plate 10 has a hole 11, and above the hole 11 there is a tube 12.
A flange 13 is fixed to the pipe 12.

この上部に濾過器5を取付ける。濾過器5の上部は出口
管6を取付け、濾過器5の下側には入口管7を取付け、
入口管7の先端にはフランジ8を固着し、フランジ13
とフランジ8は、ボルト及びナツト等で接続する。なお
覆い板10には適宜の位置9例えば平面上に等間隔に吊
り金具17を取付けである。
A filter 5 is attached to this upper part. An outlet pipe 6 is attached to the upper part of the filter 5, an inlet pipe 7 is attached to the lower side of the filter 5,
A flange 8 is fixed to the tip of the inlet pipe 7, and a flange 13
and the flange 8 are connected with bolts, nuts, etc. Note that hanging fittings 17 are attached to the cover plate 10 at appropriate positions 9, for example, at equal intervals on a plane.

第3図書第4図は容器1の7ランジ9の上部に金網14
で全周を被われた濾過材15例えばスポンジやグラスウ
ールを位置せしめその上に押え板16を乗せる。押え板
16の平面形状はフランジ9の平面形状とはy同一の形
状をしている。押え板16には吊り金具17が適宜の位
置1例えば平面上に等間隔で取付けられている。金網1
4は押え板16と分離する構造と固着された構造の二種
があるが9本例では固着された場合について説明する。
Figure 4 of the third book shows a wire mesh 14 on the top of the 7 lunges 9 of the container 1.
A filter material 15, such as a sponge or glass wool, covered all around is placed, and a presser plate 16 is placed on top of it. The planar shape of the holding plate 16 is the same as the planar shape of the flange 9. Hanging fittings 17 are attached to the holding plate 16 at appropriate positions 1, for example, at regular intervals on a plane. wire mesh 1
There are two types of 4: a structure that is separated from the presser plate 16 and a structure that is fixed to the holding plate 16, but in this example 9, a case where it is fixed will be explained.

即ち金網14濾過材15はビス等で押え板16に固着す
る。
That is, the wire mesh 14 and the filter material 15 are fixed to the holding plate 16 with screws or the like.

以上のように構成した後、原子炉圧力容器付属のポンプ
、例えば原子炉再循環系ポンプ・原子炉給水ポンプ等を
運転して容器1内に注水をして容器1内の水位を上昇さ
せ容器1内の水を、第1図第2図の場合は濾過器5を、
第3図・第4図の場合は濾過材15を経由して原子炉ウ
ェル16内に放出し、その後第1図の場合は蓋2をクレ
ーンを用いて原子炉ウェル18外に引き上け、フランジ
4.フランジ8を接続しているボルト・ナツトを解体し
濾過器5を回収する。
After configuring as described above, the pumps attached to the reactor pressure vessel, such as the reactor recirculation system pump and the reactor feed water pump, are operated to inject water into the vessel 1 to raise the water level inside the vessel 1. In the case of Fig. 1 and Fig. 2, the water in the filter 5 is filtered.
In the case of FIGS. 3 and 4, it is discharged into the reactor well 16 via the filter material 15, and then, in the case of FIG. 1, the lid 2 is lifted out of the reactor well 18 using a crane. Flange 4. The bolts and nuts connecting the flanges 8 are disassembled and the filter 5 is recovered.

第2図の場合は棟い板10をクレーンを用いて。In the case of Figure 2, the ridge board 10 is moved using a crane.

原子炉ウェル18外に引き上げ、7ランジ8とフランジ
13を接続しているボルト・ナツトを解体し。
Pull it out of the reactor well 18 and dismantle the bolts and nuts connecting 7 langes 8 and flange 13.

濾過器5を回収する。Collect the filter 5.

第3図・第4図の場合は押え板16をクレーンを用いて
、原子炉ウェル18外に引き上はビスをゆるめて押え板
16より金網14・濾過材15を回収する。
In the case of FIGS. 3 and 4, the holding plate 16 is lifted out of the reactor well 18 using a crane, and the wire mesh 14 and filter material 15 are recovered from the holding plate 16 by loosening the screws.

回収した濾過器5や濾過材15には容器1内に存在して
いたクラッドを吸着している。即ち容器1に注水した時
容器1内の水は攪拌され、これと同時にクラッドも浮遊
し、容器1内の水位上昇と共にクラッドを移動し、水が
濾過器5や濾過材15を通過する除水に含まれたクラッ
ドは付着吸収される。
The recovered filter 5 and filter material 15 adsorb the crud that was present in the container 1. That is, when water is poured into the container 1, the water in the container 1 is stirred, and at the same time, the crud is also suspended, and as the water level in the container 1 rises, the crud moves, and the water passes through the filter 5 and the filter material 15. The cladding contained in the cladding is adhered and absorbed.

本発明は以上の如く容器1内のクラッドを捕獲すること
かで舞るので、核燃料交換時及び交換後でも原子炉ウェ
ル18に付着するクラッドを低減できる。従って作業の
能率も向上し、放射線の被曝も低減できる。
Since the present invention operates by capturing the crud in the vessel 1 as described above, it is possible to reduce crud adhering to the reactor well 18 during and after nuclear fuel exchange. Therefore, work efficiency can be improved and radiation exposure can be reduced.

【図面の簡単な説明】[Brief explanation of drawings]

図面は9本発明にかかる原子炉圧力容器内のクラッドを
捕獲する一実施例を示すものでおって。 第1図〜第3図は実施例を示す側面図(部分断面を含む
)。第4図は実施例を示す部分側面図。 1・・・・・・・・・・・・容器    2・・・・・
・・・・・・・蓋3・・・・・・・・・・・・ノズル 
  4・・・・・・・・・・・・フランジ5・・・・・
・・・・・・・濾過器   6・・・・・・・・・・・
・出口管7・・・・・・・・・・・・入口管   8・
・・・・・・・・・・・フランジ9・・・・・・・・・
・・・7ランジ  10・・・・・・・・・・・・榎い
板11・・・・・・・・・・・・穴     12・・
・・・・・・・・・・管13・・・・・・・・・・・・
7ランジ  14・・・・・・・・・・・・金網15・
・・・・・・・・・・・濾過材   16・・・・・・
・・・・・・押え板17・・・・・・・・・・・・吊シ
金具  18〜・・・・・・・・・・原子炉ウェル特許
出願人 株式会社システムメンテナンス代表者 本 間
   武 第101 18 第2図 第3図 第1図 6
The drawings show an embodiment of the present invention for capturing crud in a nuclear reactor pressure vessel. FIGS. 1 to 3 are side views (including partial cross sections) showing the embodiment. FIG. 4 is a partial side view showing the embodiment. 1... Container 2...
......Lid 3...Nozzle
4...Flange 5...
・・・・・・Filter 6・・・・・・・・・・・・
・Outlet pipe 7・・・・・・・・・Inlet pipe 8・
・・・・・・・・・・・・Flange 9・・・・・・・・・
...7 lunge 10...Enoki board 11...Hole 12...
・・・・・・・・・Tube 13・・・・・・・・・・・・
7 Lunge 14・・・・・・・・・Wire mesh 15・
......Filtering material 16...
......Press plate 17...Hanging metal fittings 18~...Reactor well patent applicant Representative of System Maintenance Co., Ltd. Honma Take No. 101 18 Figure 2 Figure 3 Figure 1 Figure 6

Claims (1)

【特許請求の範囲】 原子炉圧力容器に濾過器又は濾過材を取付け。 ポンプを駆動し、原子炉圧力容器内に注水して。 原子炉圧力容器内の水位を上昇せしめ、原子炉圧力容器
内の水を濾過器を経由して原子炉ウェルに放出し、濾過
器又は濾過材にクラッドを付着せしめる原子炉圧力容器
内のクラッド捕獲方法。
[Claims] A filter or filter material is attached to a reactor pressure vessel. Drive the pump and inject water into the reactor pressure vessel. Capture of crud in the reactor pressure vessel by raising the water level in the reactor pressure vessel, releasing the water in the reactor pressure vessel to the reactor well via a filter, and causing the crud to adhere to the filter or filter material. Method.
JP57013750A 1982-01-30 1982-01-30 Method of capturing cladding in reactor pressure vessel Pending JPS58131592A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57013750A JPS58131592A (en) 1982-01-30 1982-01-30 Method of capturing cladding in reactor pressure vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57013750A JPS58131592A (en) 1982-01-30 1982-01-30 Method of capturing cladding in reactor pressure vessel

Publications (1)

Publication Number Publication Date
JPS58131592A true JPS58131592A (en) 1983-08-05

Family

ID=11841923

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57013750A Pending JPS58131592A (en) 1982-01-30 1982-01-30 Method of capturing cladding in reactor pressure vessel

Country Status (1)

Country Link
JP (1) JPS58131592A (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS56124097A (en) * 1980-03-05 1981-09-29 Hitachi Ltd Method and device for removing radioactive clad at nuclear reactor shutdown

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS56124097A (en) * 1980-03-05 1981-09-29 Hitachi Ltd Method and device for removing radioactive clad at nuclear reactor shutdown

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