JPS6244700A - Radioactive waste vessel - Google Patents
Radioactive waste vesselInfo
- Publication number
- JPS6244700A JPS6244700A JP18427985A JP18427985A JPS6244700A JP S6244700 A JPS6244700 A JP S6244700A JP 18427985 A JP18427985 A JP 18427985A JP 18427985 A JP18427985 A JP 18427985A JP S6244700 A JPS6244700 A JP S6244700A
- Authority
- JP
- Japan
- Prior art keywords
- container
- water
- waste
- radioactive waste
- hole
- 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
Links
Landscapes
- Processing Of Solid Wastes (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】
〔発明の利用分野〕
本発明は放射性廃棄物の容器に係り、特に水中において
廃棄物を容器に充填後、容器内の水を除去するのに好適
な放射性廃棄物容器に関するものである。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a container for radioactive waste, and in particular to a radioactive waste container suitable for removing water from the container after filling the container with waste in water. It is related to.
原子力発電所等の放射性物質取扱い施設から金属やコン
クリート等の固体廃棄物は、容器内に収納した後、所定
の保管場所に移送して、保管される。この廃棄物容器に
従来要求される項目は、外部へ放射能の漏洩を防止する
事、中、高レベルの放射性廃棄物を収納する場合には遮
蔽効果を持たせて容器表面の線量率を低下させる事、廃
棄物に含まれる放射能が減衰するまでの耐久性がある事
の3点である。このような項目を満足させるため。Solid waste such as metal and concrete from facilities handling radioactive materials such as nuclear power plants is stored in containers and then transferred to a designated storage location for storage. The conventional requirements for this waste container are to prevent the leakage of radioactivity to the outside, and to provide a shielding effect to reduce the dose rate on the surface of the container when storing medium to high level radioactive waste. The three points are that it is durable enough to allow the radioactivity contained in the waste to decay. To satisfy such items.
従来より多くの容器が提案されている0例えば。For example, more containers have been proposed than before.
特許57−143416.特願58−142403であ
る。しかし、高レベルの放射性廃棄物である制御棒や炉
内構造物を対象とする場合には、上記の必要な3項目に
加えて、容器からの水抜きと内部の乾燥機能が必要とな
る。これは高レベル廃棄物は比放射能が高いため、空気
中において容器に収納すると、空間線量率が増加して作
業員の被曝量が著しく増加す内に収納後、蓋を閉めてか
ら容器を水中から引き上げて、廃棄物保管場所に移送す
ることが望ましい、単に蓋を閉めただけでは、容器内に
水が残りこれが容器の腐食を加速することになる。Patent 57-143416. This is patent application No. 58-142403. However, when targeting control rods and reactor internals, which are high-level radioactive waste, in addition to the three necessary items above, functions for draining water from the container and drying the interior are required. This is because high-level waste has a high specific radioactivity, so if it is stored in a container in the air, the air dose rate will increase and the radiation exposure of workers will increase significantly. It is desirable to remove the container from the water and transport it to a waste storage area; simply closing the lid will leave water in the container, which will accelerate corrosion of the container.
本発明の目的は、上記した欠点である容器内に水が残る
問題を解決するのに好適な廃棄物容器を提供することに
ある。SUMMARY OF THE INVENTION An object of the present invention is to provide a waste container suitable for solving the above-mentioned disadvantage of water remaining in the container.
本発明は遮弊効果に影響を与えない水抜き孔と空気孔を
容器に設けることにより、容器内に残存する水の排出と
容器の乾燥を容易に行うものである。The present invention facilitates draining the water remaining in the container and drying the container by providing the container with drain holes and air holes that do not affect the shielding effect.
以下本発明の一実施例を第1図〜第4図によって説明す
る。これは、本発明を原子力発電所の廃止に伴なう炉内
構造物の解体に適用した場合である。炉内構造物を解体
する時は、圧力容器1の蓋を取り外し燃料プール2迄水
を張り、水中で解体作業を行なうことで、放射能の飛散
を防止し、水の遮弊効果により作業員の被曝量を低減す
る。解体の手順はまず取り外し可能な機器はマニピュレ
ーターにより金具を外して、水中を通して燃料プール2
へ移送する。取り外しできない機器は、プラズマアーク
により結合部を切断して1機器を燃料プール2へ移送す
る。廃棄物容器3は第2図に示すように、板厚30Ql
の鋳鋼製容器であり、内) 部空rln!よ
0.立方、。4つ、いう。S:o容器。1よ蓋を除して
から燃料プールに、あらかじめ沈める。An embodiment of the present invention will be described below with reference to FIGS. 1 to 4. This is a case where the present invention is applied to the dismantling of reactor internals accompanying the decommissioning of a nuclear power plant. When dismantling the reactor internals, remove the lid of the pressure vessel 1, fill the fuel pool 2 with water, and carry out the disassembly work underwater to prevent radioactivity from scattering and to protect workers from the water's shielding effect. reduce the amount of radiation exposure. The disassembly procedure is to first remove the metal fittings of removable equipment using a manipulator, and then put them through water into the fuel pool 2.
Transfer to. For equipment that cannot be removed, the joints are cut by plasma arc and one piece of equipment is transferred to the fuel pool 2. As shown in Fig. 2, the waste container 3 has a plate thickness of 30Ql.
It is a cast steel container with an internal space rln! Yo 0. Cubic,. Four, I say. S: o container. 1) Remove the lid and submerge it in the fuel pool.
燃料プール2内で機器は最長が90cmになるように、
プラズマアークで細かく切断する。切断片はマニピュレ
ーターで容器3に収納する。その後。The longest equipment in fuel pool 2 should be 90cm.
Cut into small pieces using a plasma arc. The cut pieces are stored in a container 3 using a manipulator. after that.
蓋4をクレーン5で降ろし、ボルト4本6をマニピュレ
ーターで締めて、容器を密閉する0次に、4箇所の吊り
金具7を用いて、クレーン5で容器を吊り上げ、水中よ
り取り出して、床面に置く。Lower the lid 4 with the crane 5, tighten the four bolts 6 with a manipulator, and seal the container.Next, use the four hanging fittings 7 to lift the container with the crane 5, take it out of the water, and place it on the floor. put it on.
この容器3には水抜き孔8と空気孔9が設けられている
。いづれの孔も容器の遮弊効果を阻害しないように、直
角に2ケ所の曲りを有し、孔に入った放射線が壁に一度
も衝突せずに、外部へ抜けない構造になっている。水抜
き孔の詳細を第3図に示すが、入口10は容器床面にあ
り、直角に2回曲り、出口11は水平向を向いている。This container 3 is provided with a drain hole 8 and an air hole 9. Each hole has two bends at right angles so as not to impede the shielding effect of the container, and the structure is such that the radiation that enters the hole never collides with the wall and escapes to the outside. The details of the drain hole are shown in FIG. 3, where the inlet 10 is located on the floor of the container and is bent twice at right angles, and the outlet 11 is oriented horizontally.
出口11の構造は、通常時は閉で相手方配管と結合する
と開になる接手で、かつ外側はネジになっており、配管
径は3./8Bであり、入口1oがら出口11までは若
干の下り勾配になっていて途中に水が滞留しない、空気
孔9は、容器上部の壁面に設けられている他は、水抜き
孔8と同等の構造になっている。床面で容器に配管接続
した時のフロー図を第4図に示す。初めに、3方弁12
と13の操作により、周囲の空気が空気孔9から容器3
に入り、内部の水が重力の作用によって水抜き孔8より
燃料プール2へ流下するようにする1次に、容器3内に
残存した水分を乾燥させる。このため、三方弁12と1
3を切り換え、乾燥空気を空気孔9から入れて水抜き孔
8から流出させる。水抜き8を出た湿った空気は、除湿
器14により水分を除去後、ブロワ−15により加熱器
16により80℃に加熱して、再度容器3に供給する。The structure of the outlet 11 is a joint that is normally closed and opens when connected to the other pipe, and has a thread on the outside, and the pipe diameter is 3. /8B, and there is a slight downward slope from the inlet 1o to the outlet 11, so water does not accumulate in the middle.The air hole 9 is the same as the drain hole 8, except that it is provided on the wall at the top of the container. It has a structure of Figure 4 shows a flow diagram when piping is connected to the container on the floor. First, 3-way valve 12
By operating steps 13 and 13, the surrounding air flows from air hole 9 to container 3.
First, water remaining in the container 3 is dried so that the water inside flows down into the fuel pool 2 from the drain hole 8 by the action of gravity. For this reason, the three-way valves 12 and 1
3 to let dry air in through the air hole 9 and out through the drain hole 8. The humid air leaving the drain 8 is heated to 80 DEG C. by a heater 16 using a blower 15 after its moisture is removed by a dehumidifier 14, and then supplied to the container 3 again.
除湿器14内に保った凝縮水は差圧計によって連続的に
測定し、増加が無くなったらブロワ−15の運転を停止
した後、バルブ17を開けて重力により燃料プールへ戻
す。水抜き孔8と空気孔9の配管を取り外した後、密閉
性を良くするため、内ネジを切った栓を取り付ける。こ
の後、トレーラ−にクレーン5を移して、貯蔵場所に運
搬する。本実施例によれば、容器内の水分を容易に除去
できる効果がある。The condensed water kept in the dehumidifier 14 is continuously measured by a differential pressure gauge, and when there is no increase, the operation of the blower 15 is stopped and the valve 17 is opened to return it to the fuel pool by gravity. After removing the piping for the drain hole 8 and air hole 9, a plug with an internal thread is attached to improve sealing performance. Thereafter, the crane 5 is transferred to a trailer and transported to a storage location. According to this embodiment, there is an effect that the moisture inside the container can be easily removed.
本発明によれば、容器内の水分を除去できることにより
、容器の腐食を抑制できる効果がある。According to the present invention, since the water inside the container can be removed, corrosion of the container can be suppressed.
第1図は原子炉解体における廃棄物容器の位置を示す配
置図、゛第2図は廃棄物容器の構造図、第3図は第2図
の出口部分の詳細図、第4図は水分除去時のフロー図で
ある。
3・・・廃棄物容器、8・・・水抜き孔、9・・・空気
孔。Figure 1 is a layout diagram showing the location of the waste container during reactor dismantling, Figure 2 is a structural diagram of the waste container, Figure 3 is a detailed view of the exit part of Figure 2, and Figure 4 is water removal. It is a flow diagram of time. 3...Waste container, 8...Drain hole, 9...Air hole.
Claims (1)
有することを特徴とする放射性廃棄物容器。1. A radioactive waste container characterized by having a hole in the container wall that corresponds to a hole when the inlet and outlet are connected in a straight line.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP18427985A JPS6244700A (en) | 1985-08-23 | 1985-08-23 | Radioactive waste vessel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP18427985A JPS6244700A (en) | 1985-08-23 | 1985-08-23 | Radioactive waste vessel |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6244700A true JPS6244700A (en) | 1987-02-26 |
Family
ID=16150534
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP18427985A Pending JPS6244700A (en) | 1985-08-23 | 1985-08-23 | Radioactive waste vessel |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6244700A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2021001860A (en) * | 2019-06-18 | 2021-01-07 | 三菱重工業株式会社 | Storage container and method for designing storage container |
-
1985
- 1985-08-23 JP JP18427985A patent/JPS6244700A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2021001860A (en) * | 2019-06-18 | 2021-01-07 | 三菱重工業株式会社 | Storage container and method for designing storage container |
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