JPS61204599A - Storage facility in base rock of radioactive waste - Google Patents

Storage facility in base rock of radioactive waste

Info

Publication number
JPS61204599A
JPS61204599A JP4528685A JP4528685A JPS61204599A JP S61204599 A JPS61204599 A JP S61204599A JP 4528685 A JP4528685 A JP 4528685A JP 4528685 A JP4528685 A JP 4528685A JP S61204599 A JPS61204599 A JP S61204599A
Authority
JP
Japan
Prior art keywords
shaft
storage
tunnel
storage facility
radioactive waste
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.)
Granted
Application number
JP4528685A
Other languages
Japanese (ja)
Other versions
JPH0582920B2 (en
Inventor
卓 石井
健二 福光
岩谷 彰
斉藤 鉄夫
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.)
Shimizu Construction Co Ltd
Original Assignee
Shimizu Construction Co Ltd
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 Shimizu Construction Co Ltd filed Critical Shimizu Construction Co Ltd
Priority to JP4528685A priority Critical patent/JPS61204599A/en
Publication of JPS61204599A publication Critical patent/JPS61204599A/en
Publication of JPH0582920B2 publication Critical patent/JPH0582920B2/ja
Granted legal-status Critical Current

Links

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】 [産業上の利用分野] この発明は、放射性廃棄物の岩盤的貯蔵設備に関する。[Detailed description of the invention] [Industrial application field] The present invention relates to a rock storage facility for radioactive waste.

[従来の技術1 使用済み核燃料を再処理する過程で発生する高レベルの
放射性廃棄物は、長期間にわたって高い放射能を有し、
また発熱量も大きいものである。
[Conventional technology 1] High-level radioactive waste generated during the process of reprocessing spent nuclear fuel has high radioactivity over a long period of time,
Furthermore, the amount of heat generated is large.

従って、これを人間環境より隔離するための最終処分を
行うに当っては、まず、ガラス固化等の充分な安全対策
を施したうえで、ある期間にわたって貯蔵管理して放射
能、発熱量を充分に減衰させる必要がある。この放射性
廃棄物の貯蔵管理は、数十年ないし数百年の長期にわた
るものであり、そのための11M段は、その期間中、放
射性廃棄物を健全に保ち、周辺の環境に放射能汚染等の
悪影響を及ぼすことなく、放射性廃棄物を冷却でき、放
射能を減衰さVることのできることが要求される。
Therefore, in final disposal to isolate it from the human environment, we must first take sufficient safety measures such as vitrification, and then store and manage it for a certain period of time to sufficiently reduce its radioactivity and calorific value. It is necessary to attenuate it. The storage management of this radioactive waste is for a long period of time, from several decades to several hundred years, and the 11M stage is designed to keep the radioactive waste healthy during this period and prevent radioactive contamination from surrounding the environment. It is required to be able to cool radioactive waste and attenuate its radioactivity without adverse effects.

そのような放射性廃棄物の貯蔵のための施設として、本
出願人は第4図および第5図に示すような岩盤的貯蔵設
備りを考えた。この岩盤的貯蔵設備りは、第4図に示す
ように山腹等の斜面を形成している岩盤1内に、一端が
大気中に開放されている下部坑道2と、下部坑道2とほ
ぼ平行な上部坑113を掘削し、この下部坑道2と上部
坑道3とを複数の貯蔵立坑4・・・によって連通し、ま
た、上部坑道3よりほぼ重心に上端が大気中に開放され
ている排気室坑道5を掘削してなるものであり、上記の
それぞれの坑道は一連の空気の流通路を形成しているも
のである。貯蔵立坑4・・・の内部には、第5図に示す
ように放射性廃棄物の固化体パッケージ6・・・が収納
される。固化体パッケージ6は、tliDJ竹廃棄物を
ガラス固化したうえでステンレス製の容器(キャニスタ
−)内に密閉したものである。また、貯蔵立坑4の下端
部J3よび下端部には、空気は流通できるが、固化体パ
ッケージ6より放射される放射線は遮蔽するラジエーシ
ョンシールド材7.8がそれぞれ取り付けられている。
As a facility for storing such radioactive waste, the applicant considered a rock-based storage facility as shown in FIGS. 4 and 5. As shown in Figure 4, this rock storage facility consists of a lower shaft 2, one end of which is open to the atmosphere, and a lower shaft 2, which is located almost parallel to the lower shaft 2, in a bedrock 1 forming a slope such as a mountainside. An upper shaft 113 is excavated, and the lower shaft 2 and upper shaft 3 are connected through a plurality of storage shafts 4..., and the upper end of the upper shaft 3 is opened to the atmosphere almost at the center of gravity. 5, and each of the above-mentioned tunnels forms a series of air flow passages. As shown in FIG. 5, solidified radioactive waste packages 6 are housed inside the storage shafts 4. The solidified package 6 is obtained by vitrifying the tliDJ bamboo waste and then sealing it in a stainless steel container (canister). Furthermore, radiation shielding materials 7 and 8 are attached to the lower end J3 and the lower end of the storage shaft 4, respectively, to allow air to flow therethrough but to block radiation emitted from the solidified material package 6.

以上のように構成されているこの岩盤的貯蔵設備りは、
岩盤1の優れた放射線遮蔽性能により、地上に悪影響を
及ぼすことなく、放射性廃棄物を長期にわたって貯蔵で
きるとともに、坑道内の空気が自然通風力によって換気
されて放射性廃棄物を効率良く冷却できるものである。
This rock-based storage facility configured as described above is
Due to the excellent radiation shielding performance of Bedrock 1, radioactive waste can be stored for a long period of time without any negative impact on the ground, and the air inside the tunnel can be ventilated by natural drafts, allowing radioactive waste to be efficiently cooled. be.

すなわち、排気立坑通5は、一般の煙突と同様にその高
さと坑道内外の空気の比重量差(すなわち温度差)に応
じた自然通風力を生じる(いわゆる煙突効果)ものであ
るから、この通風力によって第4図中の矢印で示すよう
に坑道内の空気は排気室坑道5より排出され、これに伴
って下部坑道2の開放端から外気が坑道内に流入する。
In other words, the exhaust shaft passage 5, like a general chimney, generates a natural ventilation force (so-called chimney effect) according to its height and the specific weight difference (i.e., temperature difference) between the air inside and outside the tunnel. Due to the wind force, the air in the tunnel is discharged from the exhaust chamber tunnel 5 as shown by the arrow in FIG. 4, and as a result, outside air flows into the tunnel from the open end of the lower tunnel 2.

外気は坑道内の空気に比して低温であるから、この外気
が下部坑道2を経て貯蔵立坑4内を上昇し、固化体パッ
ケージ6の周囲を通過することで、固化体パッケージ6
は冷却されることとなる。
Since the outside air has a lower temperature than the air inside the mine shaft, this outside air passes through the lower shaft 2, rises inside the storage shaft 4, and passes around the solidified material package 6, so that the solidified material package 6
will be cooled.

このようにこの岩盤的貯蔵設備りでは、何らの動力源も
必要とせずに坑道内の空気が換気されるから、そのため
の運転費を要せずに、放射性廃棄物を常に冷却できるも
のである。
In this way, this rock-based storage facility ventilates the air inside the mine shaft without requiring any power source, so it is possible to constantly cool radioactive waste without incurring operating costs. .

[発明が解決しようとする問題点] 上記のような従来考えられている岩盤的貯蔵設備りでは
、固化体パッケージ6の容器(キャニスタ−)が健全で
あれば、放射性核種が坑道内に散出することはなく、ま
た固化体パッケージ6より放射される放射線はサジ1−
ジョンシールド材7.8によって遮蔽されるから、上部
坑道3、下部坑道2の内部は汚染されることなく、安全
性は確保されている。
[Problems to be Solved by the Invention] In the conventional rock-based storage facility as described above, if the container (canister) of the solidified material package 6 is healthy, radionuclides will not be scattered into the mine shaft. In addition, the radiation emitted from the solidified package 6 is
Since they are shielded by the John shield material 7.8, the interiors of the upper tunnel 3 and lower tunnel 2 are not contaminated and safety is ensured.

しかしながら、万一の事故等でキャニスタ−が破損した
ような場合には、放射性核種は空気流に運ばれてラジエ
ーションシールド材7を通過して上部坑道3内へ流入し
てしまうことになる。そして、上部坑道3内へは、固化
体パッケージ6の貯蔵立坑4への収納もしくは取り出し
作業、あるいは坑道内の点検や監視等のために作業員が
立入る必要もあるから、作業員が被曝することも考えら
れる。
However, in the unlikely event that the canister is damaged due to an accident or the like, the radionuclides will be carried by the air flow, pass through the radiation shield material 7, and flow into the upper tunnel 3. In addition, it is necessary for workers to enter the upper shaft 3 to store or take out the solidified package 6 into the storage shaft 4, or to inspect and monitor the inside of the shaft, so the workers may be exposed to radiation. It is also possible.

また、キャニスタ−が健全であっても、上部域rU3は
固化体パッケージ6を冷Unで高温となった空気が流通
しているから好ましい作業環境とはいえず、この内部で
の作業は大変であろうと考えられる。
In addition, even if the canister is healthy, the upper area rU3 is not a favorable working environment because air that has become hot due to the cooling Un flows through the solidified package 6, making it difficult to work inside this area. It is thought that there will be.

この発明は上記の事情に鑑みてなされたもので、万一固
化体パッケージの健全性が損なわれても作業員が被曝す
ることがなく、また好適な作業環境を保つことのできる
岩盤的貯蔵設備を提供することを目的とする。
This invention was made in view of the above circumstances, and is a rock-based storage facility that prevents workers from being exposed to radiation even if the integrity of the solidified package is impaired, and that allows a suitable working environment to be maintained. The purpose is to provide

[問題点を解決するための手段] この発明は、地下の岩盤内に上下方向に離間させて上部
坑道および下部坑道を設け、その上部坑道と下部坑道と
を1つ以上の立坑道で連通してそれらの坑道内を空気が
流通するようになすとともに、上記立坑道内に放射性廃
棄物を貯蔵し、かつ上記立坑道に通じる作業坑道を設【
プ、その作業坑道と立坑道との間に空気および放射線の
通過を防止する遮蔽手段を設けてなるものである。
[Means for Solving the Problems] The present invention provides an upper shaft and a lower shaft that are spaced apart in the vertical direction in underground rock, and communicates the upper shaft and the lower shaft with one or more vertical shafts. In addition to allowing air to flow through the shafts, radioactive waste will be stored in the shafts, and a working shaft will be constructed that leads to the shafts.
A shielding means is provided between the working shaft and the vertical shaft to prevent air and radiation from passing through.

[作用] この発明の岩盤的貯蔵設備は、下部坑道、立坑道、上部
坑道が一連の空気の流通路となり、立坑道内に収納され
た放射性廃棄物の周囲を空気が流通してこれを冷却する
。また、作業坑道は放射性廃棄物の立坑道への収納もし
くは取り出し、あるいは点検等の作業のための通路とし
て用いられ、作業坑道と立坑道との間に設【プられた遮
蔽手段は、立坑道内の空気の流入と放射線の透過を防止
して作業坑道内の安全性と好適な作業環境を保つ。
[Function] In the rock storage facility of the present invention, the lower shaft, shaft shaft, and upper shaft serve as a series of air flow paths, and air circulates around the radioactive waste stored in the shaft shaft to cool it. . In addition, the working tunnel is used as a passageway for storing or removing radioactive waste into the shaft, or for inspection, etc., and the shielding means installed between the working shaft and the shaft is This prevents the inflow of air and the penetration of radiation to maintain safety and a suitable working environment within the working tunnel.

[実施例] 以下、この発明の実施例について、第1図ないし第3図
を参照して説明する。これらの図にJ5いて、上述した
従来考えられている貯蔵設置MDと同様の構成要素につ
いては、第4図および第5図と同一の符号を付し、その
詳細な説明は省略する。
[Example] Hereinafter, an example of the present invention will be described with reference to FIGS. 1 to 3. Components shown in J5 in these figures that are similar to the previously considered storage installation MD described above are designated by the same reference numerals as in FIGS. 4 and 5, and detailed explanation thereof will be omitted.

まず、第1図を参照して、この発明の第1実施例の岩盤
内貯蔵設備Aについて説明する。(第1図はこの岩盤内
貯蔵設備への要部のt断面図である。)この貯蔵設備A
は、従来の貯蔵設備D(第4図および第5図参照)と同
様に一端が大気中に開放されている下部坑道2と、排気
室坑道5に通じる上部坑道3とを連通ずる貯蔵立坑4内
に、放射性廃棄物をキャニスタ−に密閉した固化体パッ
ケージ6を収納するものである。この貯蔵設備Aにおい
ては、上部坑道3の上方に、これとほぼ平行に、地表面
へ通じる作業坑N9が掘削されている。また貯蔵立坑4
は、上部坑道3を貫通して立坑4aがさらに上方へ延び
、この立坑4aが上記作業坑道9と上部坑道3とを連通
している。この立坑4aが作業坑道9と接続する部分に
は、遮蔽材10が取り付けられている。この遮蔽材10
は、放射線を遮蔽することのできる材料(例えばコンク
リートや粘土等)が用いられ、立坑4aより空気が作業
坑道9内に流入しないよう気密性をもって取り付けられ
ている。なお、従来の貯蔵設備りおいて、貯蔵立坑4と
上部坑道3、下部坑道2との間に取り付りられていたラ
ジエーションシールド材7.8(第5図参照)は、この
貯蔵設備Aでは省略されている。
First, referring to FIG. 1, an in-rock storage facility A according to a first embodiment of the present invention will be described. (Figure 1 is a t-sectional view of the main part of this in-rock storage facility.) This storage facility A
1 is a storage shaft 4 which communicates a lower shaft 2, one end of which is open to the atmosphere, like the conventional storage facility D (see FIGS. 4 and 5), and an upper shaft 3 leading to an exhaust chamber shaft 5. A solidified package 6 in which radioactive waste is sealed in a canister is housed inside. In this storage facility A, a working shaft N9 leading to the ground surface is excavated above the upper shaft 3 and approximately parallel thereto. Also storage shaft 4
A shaft 4a extends further upward through the upper shaft 3, and this shaft 4a communicates the working shaft 9 with the upper shaft 3. A shielding material 10 is attached to a portion where the shaft 4a connects with the working tunnel 9. This shielding material 10
is made of a material capable of shielding radiation (for example, concrete or clay), and is installed airtight to prevent air from flowing into the working tunnel 9 from the vertical shaft 4a. Note that the radiation shield material 7.8 (see Figure 5) installed between the storage shaft 4, upper tunnel 3, and lower shaft 2 in conventional storage equipment is omitted in this storage equipment A. has been done.

以上の構成のもとにこの貯蔵設備Aでは、固化体パッケ
ージ6を冷却する空気の流通路と、作業のための通路が
分離され、作業員がその空気の流通路(すなわち上部坑
道3、下部坑道2)内に立入る必要がない。すなわち、
貯蔵立坑4内に固化体パッケージ6を収納する作業は、
作業坑道9より、遮蔽材10を開けた状態で行い、固化
体パッケージ6を立坑4a1上部坑3fi3内を降下さ
せて貯蔵立坑4内へ導くこととする。作業が終了すれば
速やかに遮蔽材10を閉じることにより作業坑道9には
空気が流入することがなく、また放射線も透過すること
がないから、作業坑道9の安全性と作業に好適な環境は
維持できる。貯蔵立坑4内に収納されている固化体パッ
ケージ6を取り出す作業も、上記と同様に作業坑道9よ
り行うことができ、また通常時の点検、監視等も、作業
坑道9内より行うことができる。
Based on the above configuration, in this storage facility A, the air flow path for cooling the solidified material package 6 and the work path are separated, and the worker can 2) There is no need to enter the mine shaft. That is,
The work of storing the solidified package 6 in the storage shaft 4 is as follows:
The work is carried out from the working tunnel 9 with the shielding material 10 open, and the solidified package 6 is guided down into the upper shaft 3fi3 of the shaft 4a1 and into the storage shaft 4. As soon as the work is completed, the shielding material 10 is closed to prevent air from flowing into the working tunnel 9 and to prevent radiation from passing through. Can be maintained. The work of taking out the solidified package 6 stored in the storage shaft 4 can also be performed from the working tunnel 9 in the same manner as described above, and normal inspections, monitoring, etc. can also be performed from within the working shaft 9. .

一方、固化体パッケージ6の冷却は、従来の貯蔵設備り
と全く同様に、下部坑道2に流入した低温の外気が、第
1図中の矢印で示すように貯蔵立坑4内を上昇して固化
体パッケージ6を冷却した後、上部坑道3内を第1図に
おいて紙面に直交する方向へ流れ、排気室坑道5より排
出されることでなされる。
On the other hand, the solidified material package 6 is cooled in exactly the same way as in conventional storage equipment, in which low-temperature outside air that has flowed into the lower shaft 2 rises inside the storage shaft 4 as indicated by the arrow in FIG. 1 and is solidified. After the body package 6 is cooled, it flows in the upper tunnel 3 in a direction perpendicular to the plane of the paper in FIG. 1, and is discharged from the exhaust chamber tunnel 5.

このように、この貯蔵設備Aでは、万−固化体パッケー
ジ6が健全性を損ねた場合にも、作業員に悪影響を及ぼ
すことがな(、また作業坑道9内の環境も好適に保つこ
とができる。
In this way, in this storage facility A, even if the solidified package 6 loses its integrity, it will not have a negative impact on the workers (and the environment in the working tunnel 9 can also be maintained). can.

なお、以上で説明したように、下部坑道2、上部坑道3
内へは作業員が立入る必要がないことがら、貯蔵立坑4
をぞれらの坑道2.3との間のラジエーションシールド
材は省略したが、これはもちろん従来の貯蔵設備と同様
に設けても良い。
In addition, as explained above, the lower tunnel 2 and the upper tunnel 3
Since there is no need for workers to enter the storage shaft 4.
Although the radiation shield material between the tunnels 2 and 3 is omitted, it may of course be provided in the same manner as in conventional storage equipment.

次に第2図を参照してこの発明の第2実施例の岩盤内貯
蔵設備Bについて説明する。(第2図はこの岩盤内貯蔵
設備Bの要部の置所面図である。)この貯蔵設備Bが前
述の貯蔵設備A(第1図参照)と異なるところは、固化
体パッケージ6が貯蔵キャスク11内に格納されて貯蔵
されること、およびこれに伴う貯蔵立坑4、立坑4a、
作業坑道9等の形状、寸法の変更のみであり、その他の
点では貯蔵設備へと同様であるから、以下の説明は省略
する。なお、貯蔵キャスク11は、その内部に固化体パ
ッケージ(放射性廃棄物をガラス固化したうえで主11
ニスターにW!閉じたもの)を14本ないし21本格納
する゛もので、放射線の遮蔽性能を有し、また外表面に
フィンが形成されて放熱効果が高められたものである。
Next, referring to FIG. 2, an in-rock storage facility B according to a second embodiment of the present invention will be described. (Figure 2 is a plan view of the main parts of this in-rock storage facility B.) This storage facility B differs from the storage facility A described above (see Figure 1) in that the solidified material package 6 is Being stored and stored within the cask 11, and the accompanying storage shaft 4, shaft 4a,
The only change is the shape and dimensions of the working tunnel 9, etc., and the rest is the same as the storage facility, so the following explanation will be omitted. Note that the storage cask 11 has a solidified package (radioactive waste is vitrified and
W to Nistar! It stores 14 to 21 pieces (closed type), has radiation shielding performance, and has fins formed on its outer surface to enhance its heat dissipation effect.

次に、第3図を参照してさらに別の実施例の岩器内貯蔵
設備Cについて説明する。(第3図はこの岩盤的貯蔵設
備Cの要部の透視図(斜視図)である。)この貯蔵設備
Cでは、作業坑道9は、上部坑道3と下部坑道2のほぼ
中間で、かつ隣接している他の貯蔵立坑4とのほぼ中間
に位置し、上部坑道3および下部坑道2とほぼ平行に掘
削されている。また、貯蔵立坑4の上下方向はぼ中間に
貯蔵室4bが形成され、この貯蔵室4bは上記作業坑道
9へ通じ、この貯蔵室4b内に、貯蔵キャスク11に格
納された固化体パッケージが横置きされて貯蔵される。
Next, with reference to FIG. 3, a rock artifact storage facility C according to yet another embodiment will be described. (Figure 3 is a perspective view of the main part of this rock-based storage facility C.) In this storage facility C, the working tunnel 9 is located approximately midway between the upper shaft 3 and the lower shaft 2, and is located adjacent to the upper shaft 3. It is located approximately midway between the other storage shafts 4, and is excavated approximately parallel to the upper shaft 3 and lower shaft 2. Further, a storage chamber 4b is formed approximately midway in the vertical direction of the storage shaft 4, and this storage chamber 4b communicates with the working tunnel 9, and inside this storage chamber 4b, the solidified material packages stored in the storage casks 11 are placed horizontally. placed and stored.

貯蔵室4b内に貯蔵キャスク11を収納する作業は、貯
蔵キャスク11を台車12に載置し、この台車12を作
業坑道9内をその軸線方向に移動する走行台車13に載
置し、所定位置まで貯蔵キャスク11を台車12ごと運
び、そこで台車12が横方向へ移動することで行なわれ
る。貯蔵キャスク11が貯蔵室4bに運ばれた侵、貯蔵
室4bと作業坑道9との間は遮蔽材10によって開基さ
れる。貯蔵室4b内に貯蔵されたキャスク11は、前述
の貯蔵設備A、Bと同様に、下部坑道2より貯蔵立坑1
内を上昇してくる低温の空気によって冷却され、キャス
ク11を冷却した空気は、さらに上昇して上部坑道3を
経て排気室坑道5より排出される。
The work of storing the storage cask 11 in the storage room 4b involves placing the storage cask 11 on a trolley 12, placing the trolley 12 on a traveling trolley 13 that moves in the axial direction of the working tunnel 9, and moving the storage cask 11 to a predetermined position. This is done by transporting the storage cask 11 along with the truck 12 until the point where the truck 12 moves laterally. When the storage cask 11 is transported to the storage room 4b, the space between the storage room 4b and the working tunnel 9 is opened by a shielding material 10. The casks 11 stored in the storage room 4b are transported from the lower shaft 2 to the storage shaft 1, similar to the storage facilities A and B described above.
The air that has cooled the cask 11 by being cooled by the low-temperature air rising inside the cask further rises, passes through the upper tunnel 3, and is discharged from the exhaust chamber tunnel 5.

このように、この貯蔵設備Cにおいても、固化体パッケ
ージを冷却する空気の流路と、作業通路となる作業坑道
9とは分離され、作業坑道9の安全性および好適な環境
は保つことができる。
In this way, also in this storage facility C, the air flow path for cooling the solidified material package and the working tunnel 9 serving as a working passage are separated, and the safety and suitable environment of the working tunnel 9 can be maintained. .

以上この発明の実施例について説明したが、この発明は
上記の実施例に限定されるものではない。
Although the embodiments of the present invention have been described above, the present invention is not limited to the above embodiments.

例えば、上記の実施例はいずれも排気室坑道の自然通風
力による換気によって放射性廃棄物(固化体パッケージ
)を冷却することとしたが、適宜の冷却手段を用いて坑
道内空気を冷却し、循環させるようにしても良い。また
、上部坑道、下部坑道は、岩盤内で一方向に延在させる
だけでなく、例えばそれらの坑道を網目状に設け、水平
方向に広がりをもたせてももちろん良い。
For example, in all of the above embodiments, the radioactive waste (solidified package) was cooled by ventilation using the natural draft of the exhaust chamber tunnel, but the air inside the tunnel was cooled using an appropriate cooling means and the air was circulated. You may also let them do so. Moreover, the upper tunnel and the lower tunnel may not only extend in one direction within the bedrock, but may also be provided in a mesh shape, for example, to spread out in the horizontal direction.

なお、以上の説明では省略したが、万一固化体パッケー
ジの健全性が損なわれ、放射性核種が冷W空気中に散出
した場合には、その空気が大気中に排出されることのな
いように、排気室坑道および下部坑道の開放端付近には
、高性能フィルター等の処理設備が設けられているのは
もちろんである。
Although omitted in the above explanation, in the unlikely event that the integrity of the solidified package is compromised and radionuclides are released into the cold W air, measures must be taken to prevent the air from being emitted into the atmosphere. Of course, processing equipment such as high-performance filters are installed near the open ends of the exhaust chamber tunnel and the lower tunnel.

[発明の効果] 以上、詳細に説明したようにこの発明によれば、放射性
廃棄物を冷U+する空気の流通路と、作業坑道とを分離
した構成としたから、作業坑道内の安全性と好適な作業
環境を保つことができる等の効果を有する。
[Effects of the Invention] As described above in detail, according to the present invention, the air flow path for cooling radioactive waste and the working tunnel are separated, so safety in the working tunnel is improved. This has effects such as being able to maintain a suitable working environment.

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

第1図ないし第3図は、この発明の実施例を示す図であ
る。第1図はこの発明の第1実施例の岩盤的貯蔵設備へ
の要部の立前面図、第2図はこの発明の第2実施例の岩
盤的貯蔵設備Bの要部の立前面図、第3図はこの発明゛
の第3実施例の岩盤的貯蔵設備Cの要部の透視図(斜視
図)である。 第4図および第5図は、従来考えられている岩盤的貯蔵
設備りを示す図であって、第4図はその全体概略構成を
示す透視図、第5図はその要部の立前面図である。 A、8.C・・・・・・岩盤的貯蔵設備、1・・・・・
・岩盤、2・・・・・・下部坑道、3・・・・・・上部
坑道、4・・・・・・貯蔵立坑(立坑道)、6・・・・
・・固化体パッケージ(放射性廃棄物)、9・・・・・
・作業坑道、10・・・・・・遮蔽材(遮蔽手段)。 第1図     第2図 第3図
1 to 3 are diagrams showing embodiments of the present invention. FIG. 1 is an elevational view of the main parts of the rock-based storage facility B according to the first embodiment of the present invention, and FIG. 2 is an elevational view of the main parts of the rock-based storage facility B of the second embodiment of the invention. FIG. 3 is a perspective view (perspective view) of the main parts of a rock storage facility C according to a third embodiment of the present invention. Figures 4 and 5 are diagrams showing a conventional rock-based storage facility, with Figure 4 being a perspective view showing its overall schematic configuration, and Figure 5 being an elevational view of its main parts. It is. A.8. C...Bedrock storage facility, 1...
・Bedrock, 2...Lower tunnel, 3...Upper tunnel, 4...Storage shaft (shaft), 6...
・Solid package (radioactive waste), 9...
- Working tunnel, 10... Shielding material (shielding means). Figure 1 Figure 2 Figure 3

Claims (1)

【特許請求の範囲】[Claims] 地下の岩盤内に上下方向に離間させて上部坑道および下
部坑道を設け、その上部坑道と下部坑道とを1つ以上の
立坑道で連通してそれら上部坑道、下部坑道、立坑道の
内部を空気が流通するようになすとともに、上記立坑道
内に放射性廃棄物を貯蔵し、かつ上記立坑道に通じる作
業坑道を設け、その作業坑道と上記立坑道との間に空気
および放射線の通過を防止する遮蔽手段を設けてなるこ
とを特徴とする放射性廃棄物の岩盤内貯蔵設備。
An upper shaft and a lower shaft are provided vertically apart in the underground bedrock, and the upper shaft and the lower shaft are connected by one or more shafts, and the insides of the upper shaft, lower shaft, and shaft are air-filled. A shield is provided to allow radioactive waste to flow, store radioactive waste within the shaft, provide a working shaft leading to the shaft, and prevent the passage of air and radiation between the working shaft and the shaft. An in-rock storage facility for radioactive waste, characterized by comprising a means.
JP4528685A 1985-03-07 1985-03-07 Storage facility in base rock of radioactive waste Granted JPS61204599A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4528685A JPS61204599A (en) 1985-03-07 1985-03-07 Storage facility in base rock of radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4528685A JPS61204599A (en) 1985-03-07 1985-03-07 Storage facility in base rock of radioactive waste

Publications (2)

Publication Number Publication Date
JPS61204599A true JPS61204599A (en) 1986-09-10
JPH0582920B2 JPH0582920B2 (en) 1993-11-22

Family

ID=12715069

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4528685A Granted JPS61204599A (en) 1985-03-07 1985-03-07 Storage facility in base rock of radioactive waste

Country Status (1)

Country Link
JP (1) JPS61204599A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006289244A (en) * 2005-04-08 2006-10-26 Shimizu Corp Reclamation facility
JP2012002725A (en) * 2010-06-18 2012-01-05 Taisei Corp Intermediate storage facility

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH08146876A (en) * 1994-11-21 1996-06-07 Maruzen Seisakusho:Kk Spring clip for display card holder

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58146900A (en) * 1982-02-25 1983-09-01 三菱マテリアル株式会社 Method of storing radioactive material by sealed air circulation and cooling system
JPS5931499A (en) * 1982-05-05 1984-02-20 コミツサリア・タ・レネルギ−・アトミ−ク Method and facility for processing radioactive waste

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58146900A (en) * 1982-02-25 1983-09-01 三菱マテリアル株式会社 Method of storing radioactive material by sealed air circulation and cooling system
JPS5931499A (en) * 1982-05-05 1984-02-20 コミツサリア・タ・レネルギ−・アトミ−ク Method and facility for processing radioactive waste

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006289244A (en) * 2005-04-08 2006-10-26 Shimizu Corp Reclamation facility
JP2012002725A (en) * 2010-06-18 2012-01-05 Taisei Corp Intermediate storage facility

Also Published As

Publication number Publication date
JPH0582920B2 (en) 1993-11-22

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