JPH0138559Y2 - - Google Patents

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Publication number
JPH0138559Y2
JPH0138559Y2 JP1982136663U JP13666382U JPH0138559Y2 JP H0138559 Y2 JPH0138559 Y2 JP H0138559Y2 JP 1982136663 U JP1982136663 U JP 1982136663U JP 13666382 U JP13666382 U JP 13666382U JP H0138559 Y2 JPH0138559 Y2 JP H0138559Y2
Authority
JP
Japan
Prior art keywords
cleaning
fuel
water
fuel assembly
cover
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
Application number
JP1982136663U
Other languages
Japanese (ja)
Other versions
JPS5941800U (en
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
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Priority to JP1982136663U priority Critical patent/JPS5941800U/en
Publication of JPS5941800U publication Critical patent/JPS5941800U/en
Application granted granted Critical
Publication of JPH0138559Y2 publication Critical patent/JPH0138559Y2/ja
Granted legal-status Critical Current

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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
    • Y02E30/30Nuclear fission reactors

Description

【考案の詳細な説明】 〔考案の技術分野〕 原子力発電プラントにおいて燃料として使用さ
れる燃料集合体内の燃料棒に付着した不純物を洗
浄する核燃料洗浄装置に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a nuclear fuel cleaning device for cleaning impurities attached to fuel rods in a fuel assembly used as fuel in a nuclear power plant.

〔考案の技術的背景とその問題点〕[Technical background of the invention and its problems]

軽水炉型原子力発電プラントにおいては、ウラ
ンを燃料とした燃料棒が、また、一次冷却水とし
ては純水が用いられている。特に沸騰水型原子力
発電プラント(以下BWRと略す)においては、
給水と共に原子炉内に流入した不純物が放射化さ
れてプラントにおける放射能の上昇をもたらすた
め、不純物濃度の管理には細心な注意が払われて
いる。しかしながら、一次冷却水の流量は非常に
大量であるため、給水中の不純物濃度が例え数
ppbと低いものであつても、年間に原子炉内に流
入する不純物の重量は200〜300Kgにも達する。し
かも、このようにして流入した不純物は燃料棒の
表面に付着して0.1〜0.5mm程度の層を形成するこ
とになる。このようにして付着した不純物は燃料
棒破損の原因となつたり、プラントの放射能汚染
の原因となるので、所定の時期にこの付着した不
純物を除去する必要がある。このため、従来は、
定検時に燃料集合体を炉心より取り出してプール
水中に浸漬して燃料集合体の外部よりジエツト水
を噴射して、付着物を剥離除去する方法が用いら
れてきた。第1図の従来の燃料集合体の斜視図に
示すように、燃料集合体Fは燃料棒1を8行8列
計64本格子状に配置した構造となつている。燃料
棒1は燃料被覆管の中に燃料ペレツト3を充填し
ており、その外径は12mm、長さは4mであり、長
軸方向の約50cm間隔にスペーサ2が設けられてい
る。このスペーサ2は各燃料棒1間の間隔を正し
く維持するために設けられている。燃料付着物
は、これらの燃料棒1の表面に層状に付着する。
この付着物は、主に金属酸化物例えばFe2O3
Fe3O4,NiO,CoO,CO2O等である。燃料集合
体Fは分解することが困難なため、付着物を除去
するためには燃料集合体Fの外部より上記したよ
うにジエツトノズル4からジエツト水流を吹き付
けて付着物を剥離除去する方法が行なわれてき
た。
In light water reactor type nuclear power plants, fuel rods using uranium as fuel and pure water as primary cooling water are used. Especially in boiling water nuclear power plants (hereinafter abbreviated as BWR),
Impurities that flow into the reactor along with the feed water become radioactive and cause an increase in radioactivity in the plant, so careful attention is paid to the management of impurity concentrations. However, since the flow rate of primary cooling water is extremely large, the impurity concentration in the water supply is
Even if the impurities are as low as ppb, the weight of impurities flowing into the reactor each year reaches 200 to 300 kg. Moreover, the impurities that have flowed in this way adhere to the surface of the fuel rod, forming a layer of about 0.1 to 0.5 mm. Since the impurities that have adhered in this way can cause damage to the fuel rods or cause radioactive contamination of the plant, it is necessary to remove the impurities that have adhered at a predetermined time. For this reason, conventionally,
A method has been used in which fuel assemblies are removed from the core during periodic inspections, immersed in pool water, and jet water is injected from the outside of the fuel assemblies to peel off and remove deposits. As shown in the perspective view of a conventional fuel assembly in FIG. 1, the fuel assembly F has a structure in which a total of 64 fuel rods 1 are arranged in a grid of 8 rows and 8 columns. The fuel rod 1 has a fuel cladding tube filled with fuel pellets 3, has an outer diameter of 12 mm, a length of 4 m, and is provided with spacers 2 at intervals of about 50 cm in the longitudinal direction. This spacer 2 is provided to maintain the correct spacing between each fuel rod 1. Fuel deposits adhere to the surfaces of these fuel rods 1 in a layered manner.
This deposit is mainly composed of metal oxides such as Fe 2 O 3 ,
These include Fe 3 O 4 , NiO, CoO, CO 2 O, etc. Since it is difficult to disassemble the fuel assembly F, in order to remove the deposits, a method of spraying jet water from the jet nozzle 4 from the outside of the fuel assembly F as described above is used to peel off and remove the deposits. It's here.

上記したような従来の燃料集合体の洗浄方法
は、燃料集合体の外部よりジエツト水流を吹き付
け、その水流により付着物を除去するものである
が、燃料集合体の内側にある燃料棒の付着物は除
去することが困難であつた。すなわち、燃料集合
体Fは第2図に示すように、燃料棒1を8行8列
の格子状に配置しており、かつその間隔は4mmと
小さいので、燃料集合体Fの外側に配設されたジ
エツト水流噴射ノズル4からのジエツト水を燃料
集合体Fに吹き付けても、ジエツト水は矢印のよ
うに燃料集合体の表面を流れ、内側に位置する燃
料棒1に付着している不純物にはジエツト水流が
効果的にぶつからない。このため燃料集合体の内
側の燃料棒1に付いている付着物を除去するのが
困難であつた。
The conventional method for cleaning fuel assemblies described above involves spraying jet water from the outside of the fuel assembly to remove deposits from the fuel assembly. was difficult to remove. That is, as shown in Fig. 2, fuel assembly F has fuel rods 1 arranged in a grid of 8 rows and 8 columns, and the spacing between them is as small as 4 mm, so they are arranged outside fuel assembly F. Even if the jet water from the jet water injection nozzle 4 is sprayed onto the fuel assembly F, the jet water flows on the surface of the fuel assembly as shown by the arrow and is absorbed by the impurities attached to the fuel rods 1 located inside. The jet water flow does not collide effectively. For this reason, it has been difficult to remove deposits attached to the fuel rods 1 inside the fuel assembly.

また、燃料集合体をその軸が水平方向になるよ
うに洗浄槽内に配置し、この洗浄槽の側面に設け
た洗浄液体噴射ノズルから洗浄液体を噴射すると
ともに洗浄槽を回転するように構成した燃料集合
体洗浄装置(特開昭56−151398号公報参照)が知
られている。この燃料集合体洗浄装置を用いる
と、上記従来例の洗浄方法に比べて燃料棒に付着
しているクラツドを効果的に除去することができ
るが、洗浄装置本体および配管の配置構成が複雑
であり、しかも弁の切替制御方法も複雑で、さら
に洗浄装置の設置場所も新たに必要になる等の問
題があつた。
In addition, the fuel assembly was arranged in the cleaning tank so that its axis was horizontal, and the cleaning tank was configured to be rotated while the cleaning liquid was injected from the cleaning liquid injection nozzle provided on the side of the cleaning tank. A fuel assembly cleaning device (see Japanese Unexamined Patent Publication No. 151398/1983) is known. By using this fuel assembly cleaning device, crud adhering to the fuel rods can be removed more effectively than the conventional cleaning method described above, but the cleaning device itself and the layout of the piping are complicated. Moreover, the valve switching control method is complicated, and there are also problems such as the need for a new installation location for the cleaning device.

〔考案の目的〕[Purpose of invention]

本考案は、上記の諸点に鑑みてなされたもの
で、その目的は、燃料集合体内部の燃料棒付着物
をも効率良く取り除くことができかつ新たな設置
場所を要しない簡単な構造の核燃料洗浄装置を提
供することにある。
The present invention was developed in view of the above points, and its purpose is to provide a simple structure for cleaning nuclear fuel that can efficiently remove fuel rod deposits inside fuel assemblies and does not require a new installation location. The goal is to provide equipment.

〔考案の概要〕[Summary of the idea]

本考案は、上記目的を達成するために、燃料集
合体を覆う洗浄カバーを該燃料集合体に固定する
とともに、該洗浄カバーの長軸の上下端の少なく
ともいずれか一方に洗浄水を圧入する流入口と、
前記燃料集合体の軸方向と対向する前記洗浄カバ
ーの側面に複数個設けられた洗浄水を排出する排
出口とを設け、さらに前記燃料集合体に固定され
た洗浄カバーを該燃料集合体の長軸方向を軸とし
て回転せしめる回転機構とを備え、前記排出口か
ら排出される洗浄水を直接プール水中に排出する
ように構成した核燃料洗浄装置に関するものであ
り、前記排出口はスリツト状または円形状等適宜
な形状をなしている。
In order to achieve the above object, the present invention fixes a cleaning cover that covers a fuel assembly to the fuel assembly, and provides a flow system that presses cleaning water into at least one of the upper and lower ends of the long axis of the cleaning cover. entrance and
A plurality of discharge ports for discharging cleaning water are provided on a side surface of the cleaning cover facing the axial direction of the fuel assembly, and the cleaning cover fixed to the fuel assembly is further provided with The present invention relates to a nuclear fuel cleaning device comprising a rotation mechanism configured to rotate around an axial direction and configured to discharge cleaning water discharged from the discharge port directly into pool water, wherein the discharge port has a slit shape or a circular shape. It has an appropriate shape.

〔考案の実施例〕[Example of idea]

本考案の一実施例を図面を参照して説明する。 An embodiment of the present invention will be described with reference to the drawings.

第3図は本考案の燃料洗浄装置の一部を切除し
た斜視図であり、第4図は本考案の縦断面図であ
る。これら両図に示されているように、燃料集合
体Fは複数の燃料棒1から構成されており、その
長軸方向には所定間隔ごとにスペーサ2を設けて
各燃料棒1間の間隔を正しく維持している。燃料
集合体F全体を覆う金属またはプラスチツク製の
円筒状洗浄カバー5を設けるとともに燃料集合体
Fは洗浄カバーの下部固定板15に配設した支持
具9と同じくその上部固定板14に取付けた固定
具16とによつて洗浄カバー5内の所定個所に固
定される。さらに、これら上部および下部固定板
14および15にはそれぞれ流入口17および1
8が設けてあり、洗浄水は送水ポンプ19および
20により、配管7および8を経て、流入口17
および18から洗浄カバー5内に送り込まれる。
洗浄カバー5の側面部に一個所または複数個所
(図では複数個所)の排出口6を設け、洗浄水は
この排出口6から洗浄カバー5外へ排出される。
排出口6の形状はスリツト状または円形状等適宜
な形状とすることができる。しかして、円筒状の
洗浄カバー5は回転装置によつて回転するように
構成されている。すなわち、洗浄カバー5の上部
固定板14および下部固定板15は〓状の回転支
持具13によつて支持されており、洗浄カバー5
の下端円筒側面には回転ギヤ10が配設され、こ
の回転ギヤ10はモータ12と直結したモータギ
ヤ11と噛み合う構造となつている。
FIG. 3 is a partially cut away perspective view of the fuel cleaning device of the present invention, and FIG. 4 is a longitudinal sectional view of the present invention. As shown in both of these figures, the fuel assembly F is composed of a plurality of fuel rods 1, and spacers 2 are provided at predetermined intervals in the longitudinal direction of the fuel rods 1 to control the spacing between the fuel rods 1. maintained correctly. A cylindrical cleaning cover 5 made of metal or plastic is provided to cover the entire fuel assembly F, and the fuel assembly F is fixed to the upper fixing plate 14 of the cleaning cover in the same manner as the support 9 disposed on the lower fixing plate 15 of the cleaning cover. It is fixed at a predetermined location inside the cleaning cover 5 by the tool 16. Further, these upper and lower fixing plates 14 and 15 have inlets 17 and 1, respectively.
8 is provided, and the cleaning water is supplied to the inlet 17 through the pipes 7 and 8 by water pumps 19 and 20.
and 18 into the cleaning cover 5.
One or more outlets 6 (in the figure, a plurality of outlets) are provided on the side surface of the cleaning cover 5, and the cleaning water is discharged from the outlet 6 to the outside of the cleaning cover 5.
The shape of the discharge port 6 can be any suitable shape such as a slit shape or a circular shape. Thus, the cylindrical cleaning cover 5 is configured to be rotated by a rotating device. That is, the upper fixing plate 14 and the lower fixing plate 15 of the cleaning cover 5 are supported by the cross-shaped rotation support 13, and the cleaning cover 5
A rotating gear 10 is disposed on the cylindrical side surface of the lower end, and this rotating gear 10 is structured to mesh with a motor gear 11 directly connected to a motor 12.

次に、本考案の核燃料洗浄装置の作用について
説明する。
Next, the operation of the nuclear fuel cleaning device of the present invention will be explained.

先ず、本核燃料洗浄装置は第3図には図示して
いない例えば燃料交換用プール水中に洗浄装置全
体が浸る程度に沈められている。次に、燃料棒1
の表面に付着した不純物(クラツドという)を洗
浄するための洗浄水はポンプ19および20によ
り、それぞれ配管7および8を経て洗浄カバーの
上部および下部固定板に配設した流入口17およ
び18から洗浄カバー内に送り込まれる。ところ
で、洗浄カバー5は回転装置によつて回転されて
いるため、流入口17および18から流入し燃料
棒1の間隙を流れ排出口6に向つて流れる洗浄水
も洗浄カバー5の回転に伴なつて回転するように
なる。この様子を示したのが第5図である。すな
わち、洗浄カバー5の回転に伴ない燃料集合体F
の内部に送り込まれた洗浄水も図示のように回転
方向の力が加わり、あるいは乱れを生じるので燃
料棒1に付着したクラツドを効率的に剥離除去す
ることができる。
First, the present nuclear fuel cleaning apparatus is submerged in water, for example, a fuel exchange pool (not shown in FIG. 3), to such an extent that the entire cleaning apparatus is immersed. Next, fuel rod 1
Cleaning water for cleaning impurities (called crud) adhering to the surface of the cleaning cover is pumped by pumps 19 and 20 through pipes 7 and 8, respectively, and from inlets 17 and 18 provided on the upper and lower fixing plates of the cleaning cover. sent into the cover. By the way, since the cleaning cover 5 is rotated by a rotating device, the cleaning water that flows in from the inlets 17 and 18, flows through the gap between the fuel rods 1, and flows toward the discharge port 6 also flows with the rotation of the cleaning cover 5. It will start rotating. FIG. 5 shows this situation. That is, as the cleaning cover 5 rotates, the fuel assembly F
The cleaning water sent into the fuel rod 1 is also subjected to a force in the rotational direction as shown in the figure, or is disturbed, so that the crud adhering to the fuel rod 1 can be efficiently peeled off and removed.

洗浄対象となる燃料集合体には大量の放射能を
有する不純物であるクラツドが付着しているの
で、洗浄水中にも放射能が含まれることとなる。
したがつて、この様に大量の放射能が付着した燃
料集合体を処理する作業は放射能の飛散を防止す
るため、専用のプール水の中で実施される。
Since the fuel assembly to be cleaned has a large amount of radioactive impurity crud attached to it, the cleaning water will also contain radioactivity.
Therefore, processing of fuel assemblies with such a large amount of radioactivity is carried out in a dedicated pool of water to prevent radioactivity from scattering.

本考案に係る洗浄作業も例えば燃料交換用プー
ル水中で行われ、洗浄装置からの洗浄水により取
り除かれた放射能を含むクラツドはプール水中に
排出することになるが、このプール水中のクラツ
ドは既設の専用の放射能捕集装置例えばイオン交
換塔等により除去され、ドラム缶詰め等の方法に
より処理されている。
The cleaning work according to the present invention is also carried out in the water of a fuel exchange pool, for example, and the radioactive debris removed by the cleaning water from the cleaning equipment is discharged into the pool water. The radioactivity is removed using a dedicated radioactivity collection device such as an ion exchange tower, and then processed by methods such as drum canning.

次に、本考案の核燃料洗浄装置(以下本実施例
と略す)と洗浄水排出口が上端面または下端面に
ある従来の燃料集合体洗浄装置(以下従来例と略
す)の洗浄効果について説明する。
Next, the cleaning effects of the nuclear fuel cleaning device of the present invention (hereinafter referred to as the present embodiment) and the conventional fuel assembly cleaning device in which the cleaning water outlet is located on the upper or lower end surface (hereinafter referred to as the conventional example) will be explained. .

洗浄対象となる燃料集合体は長さ4m程度の柱
状をなしている。このため従来例のように洗浄水
排出口が上端面に設置したものでは、燃料集合体
の中程(上下端より2m程度)の位置では水流が
定常流となつてしまい、水流の乱れを起こすこと
は不可能となり、洗浄効率は第6図のようにな
る。
The fuel assembly to be cleaned has a columnar shape with a length of about 4 m. For this reason, in conventional models where the cleaning water outlet is installed on the upper end surface, the water flow becomes a steady flow at the middle of the fuel assembly (approximately 2 m from the upper and lower ends), causing turbulence in the water flow. This becomes impossible, and the cleaning efficiency becomes as shown in FIG.

一方、本実施例のように洗浄水排出口を回転す
る洗浄カバーの側面に複数個設けたものでは上部
または下部の流入口から流入した洗浄水は近傍の
排出口に向かつて流れるため乱れを生じ易くな
る。この様な排出口がカバーの側面下方から上方
にかけて複数個設置されているため燃料集合体内
部全体について水流の乱れを生じるので、洗浄効
果が大きくなり、第6図に示すように従来例に比
べて約20%以上洗浄効率が高い。
On the other hand, in the case where a plurality of washing water outlets are provided on the side surface of the rotating washing cover as in this embodiment, the washing water flowing in from the upper or lower inlet will flow toward the nearby outlet, causing turbulence. It becomes easier. Since a plurality of such discharge ports are installed from the lower side to the upper side of the cover, turbulence of water flow is generated throughout the inside of the fuel assembly, resulting in a greater cleaning effect, compared to the conventional example, as shown in Figure 6. The cleaning efficiency is about 20% or more.

なお、上記実施例では、洗浄水は洗浄カバーの
両端部から流入する場合について説明したが燃料
棒へのクラツドの付着具合によつては洗浄カバー
の上、下端部のいずれか一方からあるいは交互に
洗浄水を流入するようにしてもよいことは勿論で
ある。
In the above embodiment, the cleaning water flows from both ends of the cleaning cover, but depending on the degree of adhesion of the crud to the fuel rods, the cleaning water may flow from either the top or bottom of the cleaning cover, or alternately. Of course, cleaning water may also be allowed to flow in.

〔考案の効果〕[Effect of idea]

以上説明したように、本考案によれば、下記
〜のような効果を奏する。
As explained above, according to the present invention, the following effects are achieved.

洗浄水排出口を洗浄カバーの側面のみに設け
かつ洗浄カバーを回転しているので、上下方向
から流入した洗浄水が洗浄カバーの側面に設け
た排水口に向かうときに回転力を受け水流の乱
れを生じ、この乱れにより燃料棒に付着したク
ラツドを効率よく取り去ることができる。
Since the cleaning water outlet is provided only on the side of the cleaning cover and the cleaning cover is rotated, when the cleaning water flowing in from above and below goes to the drain provided on the side of the cleaning cover, it receives rotational force and causes disturbances in the water flow. This turbulence makes it possible to efficiently remove crud adhering to the fuel rods.

従来の洗浄装置に比べて分岐配管および弁が
少ないので、構造が簡単でかつ製作も容易であ
る。
Since there are fewer branch pipes and valves than conventional cleaning devices, the structure is simple and easy to manufacture.

定検時に炉心より取り出した使用中の燃料集
合体をそのままの姿勢で洗浄装置内に挿入でき
るので、洗浄作業が能率良く実施でき、かつ作
業員の被曝防止に寄与する。
Since fuel assemblies in use that are removed from the reactor core during periodic inspections can be inserted into the cleaning device in the same position, the cleaning work can be carried out efficiently and contributes to preventing worker exposure to radiation.

既設のプール水処理装置が利用できるので、
新たな廃液処理施設を必要としない。
Existing pool water treatment equipment can be used, so
No new waste liquid treatment facility is required.

プール水中で洗浄が行われるので、敷地内に
新たな用地を必要とせず、また汚染地域が拡散
しない。
Since cleaning is carried out in the pool water, no new land is required on the premises, and contaminated areas are not spread.

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

第1図は従来の燃料集合体の斜視図、第2図は
従来の燃料汚染方法の概略図、第3図は一部を切
除した本考案の核燃料洗浄装置の斜視図、第4図
は第3図の本考案の核燃料洗浄装置の縦断面図、
第5図は本考案にかゝる燃料集合体内の洗浄水の
流れを説明する横断面図、第6図は本考案と従来
例の洗浄効率を比較した図である。 F……燃料集合体、1……燃料棒、5……洗浄
カバー、6……排出口、7,8……配管、9……
支持具、10,11……ギヤ、12……モータ、
13……回転支持具、14,15……固定板、1
6……固定具、17,18……流入口、19,2
0……ポンプ。
FIG. 1 is a perspective view of a conventional fuel assembly, FIG. 2 is a schematic diagram of a conventional fuel contamination method, FIG. 3 is a partially cutaway perspective view of the nuclear fuel cleaning device of the present invention, and FIG. Fig. 3 is a vertical cross-sectional view of the nuclear fuel cleaning device of the present invention;
FIG. 5 is a cross-sectional view illustrating the flow of cleaning water in the fuel assembly according to the present invention, and FIG. 6 is a diagram comparing the cleaning efficiency of the present invention and a conventional example. F... Fuel assembly, 1... Fuel rod, 5... Cleaning cover, 6... Discharge port, 7, 8... Piping, 9...
Support, 10, 11... Gear, 12... Motor,
13... Rotating support tool, 14, 15... Fixed plate, 1
6...Fixing tool, 17, 18...Inflow port, 19,2
0...Pump.

Claims (1)

【実用新案登録請求の範囲】 (1) 燃料集合体を覆う洗浄カバーを該燃料集合体
に固定するとともに、該洗浄カバーの長軸の上
下端の少なくともいずれか一方に洗浄水を圧入
する流入口と、前記燃料集合体の軸方向と対向
する前記洗浄カバーの側面に複数個設けられた
洗浄水を排出する排出口とを設け、さらに前記
燃料集合体に固定された洗浄カバーを該燃料集
合体の長軸方向を軸として回転せしめる回転機
構とを備え、前記排出口から排出される洗浄水
は直接プール水中に排出するように構成したこ
とを特徴とする核燃料洗浄装置。 (2) 排出口はスリツト状または円形状である実用
新案登録請求の範囲第1項記載の核燃料洗浄装
置。
[Claims for Utility Model Registration] (1) A cleaning cover that covers a fuel assembly is fixed to the fuel assembly, and an inlet for pressurizing cleaning water into at least one of the upper and lower ends of the long axis of the cleaning cover. and a plurality of discharge ports for discharging cleaning water provided on a side surface of the cleaning cover facing the axial direction of the fuel assembly, and further displacing the cleaning cover fixed to the fuel assembly from the fuel assembly. What is claimed is: 1. A nuclear fuel cleaning device comprising: a rotation mechanism configured to rotate about the long axis direction of the nuclear fuel cleaning device, and the cleaning water discharged from the discharge port is configured to be discharged directly into pool water. (2) The nuclear fuel cleaning device according to claim 1, wherein the discharge port is slit-shaped or circular.
JP1982136663U 1982-09-10 1982-09-10 Nuclear fuel cleaning equipment Granted JPS5941800U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1982136663U JPS5941800U (en) 1982-09-10 1982-09-10 Nuclear fuel cleaning equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1982136663U JPS5941800U (en) 1982-09-10 1982-09-10 Nuclear fuel cleaning equipment

Publications (2)

Publication Number Publication Date
JPS5941800U JPS5941800U (en) 1984-03-17
JPH0138559Y2 true JPH0138559Y2 (en) 1989-11-17

Family

ID=30307207

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1982136663U Granted JPS5941800U (en) 1982-09-10 1982-09-10 Nuclear fuel cleaning equipment

Country Status (1)

Country Link
JP (1) JPS5941800U (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS52122793A (en) * 1976-04-09 1977-10-15 Hitachi Ltd Washing method and device of nuclear fuel in use in reactor equipment
JPS56151398A (en) * 1980-04-25 1981-11-24 Tokyo Shibaura Electric Co Cleaning device for fuel assembly

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS52122793A (en) * 1976-04-09 1977-10-15 Hitachi Ltd Washing method and device of nuclear fuel in use in reactor equipment
JPS56151398A (en) * 1980-04-25 1981-11-24 Tokyo Shibaura Electric Co Cleaning device for fuel assembly

Also Published As

Publication number Publication date
JPS5941800U (en) 1984-03-17

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