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JP4329076B2 - Radioactive waste disposal facility and its construction method - Google Patents
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JP4329076B2 - Radioactive waste disposal facility and its construction method - Google Patents

Radioactive waste disposal facility and its construction method Download PDF

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JP4329076B2
JP4329076B2 JP2004223989A JP2004223989A JP4329076B2 JP 4329076 B2 JP4329076 B2 JP 4329076B2 JP 2004223989 A JP2004223989 A JP 2004223989A JP 2004223989 A JP2004223989 A JP 2004223989A JP 4329076 B2 JP4329076 B2 JP 4329076B2
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grout
radioactive waste
layer
waste disposal
tunnel
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遵 延藤
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Shimizu Corp
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Description

本発明は、放射性廃棄物処分施設およびその築造方法に関する。   The present invention relates to a radioactive waste disposal facility and a construction method thereof.

高レベル放射性廃棄物の処分については、高レベル放射性廃棄物をガラスと混ぜて固化したガラス固化体を炭素鋼等からなるオーバーパックで密閉した後、300mを超える地下深部の安定した岩盤に形成された坑道に、ベントナイトで被覆して封じ込めることが計画されている。
しかし、岩盤等の地盤には破砕帯等の割れ目が存在するため、掘削時に多量の湧水が発生することが予想され、円滑な施工のためには、ある程度止水しながら掘削していく必要がある。また、坑道周辺の地下水を低下させることは、地表面付近の酸化性地下水の流入を招き、オーバーパックの腐食を促進するおそれがあり、この点からも坑道内への湧水を低減する必要がある。
トンネル工事で一般に用いられている岩盤止水工法としては、セメント系材料によるグラウト工法があるが、セメント系グラウト材は、放射性廃棄物処分において重要なバリアとなるベントナイトに悪影響を与え、その性能を劣化させることが知られている。そのため、ベントナイトを注入材料とするグラウト工法について研究が進められている。
他方、特許文献1には、沿岸海底下の地層中に放射性廃棄物を埋蔵処分した場合でも、地下水流動による放射性汚染を防止することができる放射性廃棄物処分場の発明が開示されている。
特開平5−203797号公報 (第2−3頁、第1図)
Regarding the disposal of high-level radioactive waste, the solidified glass solidified by mixing high-level radioactive waste with glass and sealed with an overpack made of carbon steel, etc., is then formed on a stable bedrock in the depth of over 300m. It is planned to cover the mine with bentonite and contain it.
However, because there are fractures such as crush zones in the ground such as rock mass, it is expected that a large amount of spring water will be generated during excavation. There is. In addition, lowering the groundwater around the tunnel leads to the inflow of oxidizing groundwater near the ground surface, which may promote overpack corrosion. From this point as well, it is necessary to reduce the spring water into the tunnel. is there.
There is a grouting method using cement-based materials as a rock-water waterproofing method that is generally used in tunnel construction, but cement-based grouting materials have an adverse effect on bentonite, which is an important barrier in the disposal of radioactive waste, and its performance is reduced. It is known to deteriorate. For this reason, research is being conducted on the grout method using bentonite as an injection material.
On the other hand, Patent Document 1 discloses an invention of a radioactive waste disposal site that can prevent radioactive contamination due to groundwater flow even when radioactive waste is buried in a formation under a coastal seabed.
JP-A-5-203797 (page 2-3, FIG. 1)

しかしながら、ベントナイトグラウトは十分な強度を有していないため、深部トンネル工事のように高水圧下における掘削工事では、坑道内へ湧水が流入し、打設したベントナイトグラウト材料が坑道内へ押し返されることが懸念される。
また、特許文献1に記載されたような、沿岸海底下の地層中に放射性廃棄物を埋蔵処分する方法は、海洋投棄との関係や具体性の点から現段階では困難とされており、地下深部に放射性廃棄物を埋蔵処分する方法が最も有効だと考えられている。
However, since bentonite grout does not have sufficient strength, in excavation work under high water pressure such as deep tunnel construction, spring water flows into the tunnel and the bentonite grout material pushed back into the tunnel. There is a concern.
In addition, the method of depositing radioactive waste in the stratum beneath the coastal seabed as described in Patent Document 1 is considered difficult at this stage from the viewpoint of the relationship with the ocean dumping and the concreteness. The method of burying radioactive waste in the deep part is considered to be the most effective.

本発明は、上述する問題点に鑑みてなされたもので、坑道内に充填されるベントナイトまたはベントナイト混合土に悪影響を与えることなく、止水が可能な放射性廃棄物処分施設およびその築造方法を提供することを目的とする。   The present invention has been made in view of the above-described problems, and provides a radioactive waste disposal facility capable of stopping water without adversely affecting bentonite or bentonite mixed soil filled in a tunnel, and a method for constructing the same. The purpose is to do.

上記目的を達成するため、本発明に係る放射性廃棄物処分施設では、放射性廃棄物を貯蔵するために地盤内に形成された坑道からなる放射性廃棄物処分施設であって、前記坑道の周壁として形成された地盤がベントナイトグラウトまたは粘土グラウトからなる第一改良地盤層と、当該第一改良地盤層の外周部に形成されたセメント系グラウトまたはシリカ系グラウトからなる第二改良地盤層とを備えることを特徴とする。
本発明では、坑道の周壁としてベントナイトグラウトまたは粘土グラウトからなる第一改良地盤層を形成するので、坑道内に充填されるベントナイトまたはベントナイト混合土に悪影響を与えることなく、止水することができる。また、第一改良地盤層の外周部にはセメント系グラウトまたはシリカ系グラウトからなる強度の高い第二改良地盤層を形成しているので、高水圧下においても、湧水が坑道内へ流入することがない。
In order to achieve the above object, the radioactive waste disposal facility according to the present invention is a radioactive waste disposal facility comprising a tunnel formed in the ground for storing radioactive waste, and is formed as a peripheral wall of the tunnel. The first improved ground layer made of bentonite grout or clay grout, and the second improved ground layer made of cement-based grout or silica-based grout formed on the outer periphery of the first improved ground layer. Features.
In the present invention, since the first improved ground layer made of bentonite grout or clay grout is formed as the peripheral wall of the tunnel, water can be stopped without adversely affecting the bentonite or bentonite mixed soil filled in the tunnel. Further, since the outer peripheral portion of the first ground improved layer to form a second ground improved layer high strength consisting of cementitious grout or silica-based grout, even under high water pressure, spring water flows into the gallery There is nothing.

また、本発明に係る放射性廃棄物処分施設の築造方法では、切羽より前方の坑道としての掘削領域を囲繞する前記第二改良地盤層を形成し、次いで前記第二改良地盤層の内方の地盤に前記第一改良地盤層を形成して坑道の周壁となし、その後、前記掘削領域を掘削することを特徴とする。
本発明では、切羽より前方の掘削領域を囲繞する、セメント系グラウトまたはシリカ系グラウトからなる第二改良地盤層を形成し、さらに当該第二改良地盤層の内方にベントナイトグラウトまたは粘土グラウトからなる第一改良地盤層を形成した後、坑道を掘削するので、高水圧下においても、坑道内への湧水の流入を防止し、円滑に工事を進めることができる。
Further, in the method for constructing the radioactive waste disposal facility according to the present invention, the second improved ground layer surrounding the excavation area as a tunnel ahead of the face is formed, and then the inner ground of the second improved ground layer The first improved ground layer is formed as a peripheral wall of a mine shaft, and then the excavation area is excavated.
In the present invention, a second improved ground layer made of cement grout or silica grout surrounding the excavation area in front of the face is formed, and further, bentonite grout or clay grout is formed inside the second improved ground layer. Since the tunnel is excavated after the first improved ground layer is formed, the inflow of spring water into the tunnel can be prevented even under high water pressure, and the construction can proceed smoothly.

本発明によれば、坑道の周壁としてベントナイトグラウトまたは粘土グラウトからなる第一改良地盤層を形成し、さらにその外周部にセメント系グラウトまたはシリカ系グラウトからなる第二改良地盤層を形成するので、坑道内に充填されるベントナイトまたはベントナイト混合土に悪影響を与えることなく、止水が可能な放射性廃棄物処分施設を実現することができる。
また、本発明によれば、切羽より前方の掘削領域を囲繞する、セメント系グラウトまたはシリカ系グラウトからなる第二改良地盤層を形成し、さらに当該第二改良地盤層の内方にベントナイトグラウトまたは粘土グラウトからなる第一改良地盤層を形成した後、坑道を掘削するので、高水圧下においても、坑道内への湧水の流入を防止し、円滑に工事を進めることができる。
According to the present invention, the first improved ground layer made of bentonite grout or clay grout is formed as the peripheral wall of the tunnel, and further the second improved ground layer made of cement-based grout or silica-based grout is formed on the outer periphery thereof. A radioactive waste disposal facility capable of stopping water can be realized without adversely affecting bentonite or bentonite mixed soil filled in the mine shaft.
The present according to the invention, surrounding the front of the excavation area from the working face to form a second improved ground layer made of cement grout or silica-based grout, further bentonite grout or inwardly of the second improved ground layer Since the tunnel is excavated after the first improved ground layer made of clay grout is formed, the inflow of spring water into the tunnel is prevented even under high water pressure, and the construction can proceed smoothly.

以下、本発明に係る放射性廃棄物処分施設について図面に基いて説明する。
図1は、本発明に係る放射性廃棄物処分施設の一例を示す側断面図およびA−A矢視断面図である。
図1に示すように、本発明に係る放射性廃棄物処分施設は、放射性廃棄物5を貯蔵するために地盤G内に形成された断面視円形の坑道3と、坑道3の周壁として形成されたベントナイトグラウトまたは粘土グラウトからなる第一改良層2(第一改良地盤層)と、第一改良層2の外周部に形成されたセメント系グラウトまたはシリカ系グラウトからなる第二改良層1(第二改良地盤層)とから構成される。
ここで、第一改良層2は、止水を主目的とし、透水係数10−5〜10−6cm/s程度かそれ以下の値が得られるようにするのが好ましい。一方、第二改良層1は、ある程度の止水とともに強度も兼ね備えることを目的としており、透水係数は10−3〜10−5cm/s程度のいわゆる難透水としての機能を有するものが考えられる。
Hereinafter, the radioactive waste disposal facility according to the present invention will be described with reference to the drawings.
FIG. 1 is a side cross-sectional view and a cross-sectional view taken along line AA showing an example of a radioactive waste disposal facility according to the present invention.
As shown in FIG. 1, the radioactive waste disposal facility according to the present invention is formed as a cross-sectional circular tunnel 3 formed in the ground G for storing the radioactive waste 5 and a peripheral wall of the tunnel 3. First improvement layer 2 (first improvement ground layer) made of bentonite grout or clay grout, and second improvement layer 1 made of cement-type grout or silica-type grout formed on the outer periphery of the first improvement layer 2 (second Improved ground layer) .
Here, the first improvement layer 2 is mainly intended to stop water, and it is preferable to obtain a water permeability coefficient of about 10-5 to 10-6 cm / s or less. On the other hand, the 2nd improvement layer 1 aims at having intensity | strength with a certain amount of water stop, and the thing which has a function as what is called a poor water permeability whose water permeability coefficient is about 10 <-3> -10 <-5> cm / s is considered.

坑道3内はベントナイト4で満たされており、ベントナイト4中に、炭素鋼等からなるオーバーパックで密閉された放射性廃棄物5が貯蔵される。ここで、ベントナイト4は、地盤Gからの圧力を和らげるための緩衝材の役目をしている。また、オーバーパックが破損した場合には、ベントナイト4の透水性が低いため、放射性廃棄物5 の移行が遅延し、さらにイオン交換性によって放射性廃棄物5 がベントナイト4 に吸着される。   The inside of the tunnel 3 is filled with bentonite 4, and radioactive waste 5 sealed with an overpack made of carbon steel or the like is stored in the bentonite 4. Here, the bentonite 4 serves as a cushioning material for relieving the pressure from the ground G. Further, when the overpack is broken, the permeability of the bentonite 4 is low, so that the transfer of the radioactive waste 5 is delayed, and the radioactive waste 5 is adsorbed on the bentonite 4 due to the ion exchange property.

セメント系グラウトまたはシリカ系グラウトは高い強度を有しており、高水圧下でも機能することができる。セメント系グラウトは、セメント量が多くなると、ベントナイトに悪影響を及ぼすため、セメント量が少ないものが望ましい。また、シリカ系グラウトは、ベントナイトに悪影響を与えにくい中性に近いもの、例えば、シリカヒュームとグラウト用石灰を混合し、強度を確保しながらpH値を弱アルカリに抑えたグラウト材が考えられる。   Cement grout or silica grout has high strength and can function even under high water pressure. A cement-type grout having a small amount of cement is desirable because a large amount of cement adversely affects bentonite. Further, silica-based grout is considered to be a near-neutral one that does not adversely affect bentonite, for example, a grout material in which silica fume and grout lime are mixed and the pH value is suppressed to a weak alkali while ensuring strength.

一方、ベントナイトグラウトは、ベントナイトに水を加えたものであり、粘性を抑えるためにエタノールや塩水により希釈してもよく、クニゲルV1(登録商標)、クニゲルV0(登録商標)、ボルクレイ(登録商標)等のベントナイトが好適である。また、粘土グラウトは、一般の粘土に水を加えたものであり、細粒で、粘性が小さく、沈降・沈積後の安定性の大きい粘土が望ましい。   On the other hand, bentonite grout is obtained by adding water to bentonite and may be diluted with ethanol or salt water in order to suppress viscosity. Kunigel V1 (registered trademark), Kunigel V0 (registered trademark), Volclay (registered trademark) Bentonite such as is preferred. The clay grout is obtained by adding water to general clay, and is preferably a fine-grained clay with low viscosity and high stability after sedimentation / deposition.

本実施形態による放射性廃棄物処分施設では、坑道3の周壁としてベントナイトグラウトまたは粘土グラウトからなる第一改良層2を形成するので、坑道3内に充填されるベントナイト4に悪影響を与えることなく、止水することができる。また、第一改良層2の外周部にセメント系グラウトまたはシリカ系グラウトからなる強度の高い第二改良層1を形成しているので、高水圧下においても、坑道3内へ湧水が流入することがない。   In the radioactive waste disposal facility according to the present embodiment, the first improvement layer 2 made of bentonite grout or clay grout is formed as the peripheral wall of the tunnel 3, so that the bentonite 4 filled in the tunnel 3 is not adversely affected and is stopped. Can be water. Moreover, since the high strength 2nd improvement layer 1 which consists of cement-type grout or a silica-type grout is formed in the outer peripheral part of the 1st improvement layer 2, spring water flows in into the tunnel 3 under high water pressure. There is nothing.

次に、本発明に係る放射性廃棄物処分施設の築造方法について説明する。以下、掘削方向を「前」とし、逆方向を「後」とする。
図2は、本発明に係る放射性廃棄物処分施設の築造方法を示す側断面図である。
先ず、既に形成された坑道3前端の切羽6から前方の掘削領域R(20〜30m程度)に向けて放射状に複数の鋼管7…を打設する。そして、鋼管7…から地盤にセメント系グラウトまたはシリカ系グラウトを注入し、掘削領域Rの周囲に円筒状の第二改良層1aを形成する。また、掘削領域Rの前端部には、第二改良層1aとの間に第一改良層2の厚み分の間隙8を設けた状態で、円盤状の第二改良層1bを形成する(図2(a)参照)。
次いで、鋼管7…を引抜き、新たに、切羽6から前方の掘削領域Rに向けて放射状に複数の鋼管7’…を打設する。そして、鋼管7’…から地盤にベントナイトグラウトまたは粘土グラウトを注入し、第二改良層1aの内側に円筒状の第一改良層2aを形成する。この際、第二改良層1bと第二改良層1a間の間隙8にも第一改良層2aを形成する(図2(b)参照)。
その後、鋼管7’…を引抜き、切羽6から前方に向けて坑道3を掘削する(図2(c)参照)。この際、第二改良層1bまで掘削せず、第二改良層1bの後方に地山G’を部分的に残しておく。これにより、第二改良層1bを透過した湧水が坑道3内に侵入するのを防止することができる。
以下、20〜30m程度の所定ピッチで上記作業を繰返すことにより、放射性廃棄物処分施設を築造する。
Next, the construction method of the radioactive waste disposal facility according to the present invention will be described. Hereinafter, the excavation direction is “front”, and the reverse direction is “rear”.
FIG. 2 is a side sectional view showing a method for constructing a radioactive waste disposal facility according to the present invention.
First, a plurality of steel pipes 7 are radially radiated from the face 6 at the front end of the already formed mine shaft 3 toward the front excavation region R (about 20 to 30 m). Then, cement-based grout or silica-based grout is injected into the ground from the steel pipes 7 to form the cylindrical second improvement layer 1a around the excavation region R. In addition, a disc-shaped second improvement layer 1b is formed at the front end of the excavation region R in a state where a gap 8 corresponding to the thickness of the first improvement layer 2 is provided between the excavation region R and the second improvement layer 1a (see FIG. 2 (a)).
Next, the steel pipes 7 are pulled out, and a plurality of steel pipes 7 'are newly radiated from the face 6 toward the front excavation region R. Then, bentonite grout or clay grout is poured into the ground from the steel pipes 7 '... to form a cylindrical first improved layer 2a inside the second improved layer 1a. At this time, the first improved layer 2a is also formed in the gap 8 between the second improved layer 1b and the second improved layer 1a (see FIG. 2B).
Thereafter, the steel pipes 7 'are pulled out, and the mine shaft 3 is excavated forward from the face 6 (see FIG. 2C). At this time, the natural ground G ′ is partially left behind the second improved layer 1b without excavating to the second improved layer 1b. Thereby, it can prevent that the spring water which permeate | transmitted the 2nd improvement layer 1b penetrate | invades in the mine shaft 3. FIG.
Hereinafter, the radioactive waste disposal facility is constructed by repeating the above work at a predetermined pitch of about 20 to 30 m.

なお、図2(d)に示すように、坑道3の端部では、端部周縁と周壁の間に間隙を設けずに第二改良層1cを形成するとともに、第二改良層1cの内側全面にわたって第一改良層2cを形成する。
このようにして、放射性廃棄物処分施設が築造されるが、完成後は図1に示したように、炭素鋼等からなるオーバーパックで密閉された放射性廃棄物5を坑道3内に搬入し、放射性廃棄物5と坑道3の周壁との空間にベントナイト4を充填する。この結果、放射性廃棄物5は半永久的に貯蔵即ち処分されることになる。
In addition, as shown in FIG.2 (d), while forming the 2nd improvement layer 1c in the edge part of the mine shaft 3 without providing a gap | interval between an edge part periphery and a surrounding wall, the inner side whole surface of the 2nd improvement layer 1c The first improved layer 2c is formed over the entire area.
In this way, a radioactive waste disposal facility is built, but after completion, as shown in FIG. 1, the radioactive waste 5 sealed with an overpack made of carbon steel or the like is carried into the mine shaft 3, Bentonite 4 is filled in the space between the radioactive waste 5 and the peripheral wall of the tunnel 3. As a result, the radioactive waste 5 is stored or disposed of semipermanently.

本実施形態による放射性廃棄物処分施設の築造方法では、切羽6より前方の掘削領域Rを囲繞する、セメント系グラウトまたはシリカ系グラウトからなる第二改良層1a、1bを形成し、さらに第二改良層1aの内側にベントナイトグラウトまたは粘土グラウトからなる第一改良層2aを形成した後、坑道3を掘削するので、高水圧下においても、坑道3内への湧水の流入を防止し、円滑に工事を進めることができる。   In the construction method of the radioactive waste disposal facility according to the present embodiment, the second improvement layers 1a and 1b made of cement grout or silica grout surrounding the excavation region R in front of the face 6 are formed, and further the second improvement. After the first improved layer 2a made of bentonite grout or clay grout is formed inside the layer 1a, the tunnel 3 is excavated. Therefore, even under high water pressure, the inflow of spring water into the tunnel 3 can be prevented and smoothly Construction can proceed.

以上、本発明に係る放射性廃棄物処分施設の実施形態について説明したが、本発明は上記の実施形態に限定されるものではなく、その趣旨を逸脱しない範囲で適宜変更可能である。例えば、上記の実施形態では、放射性廃棄物処分施設の断面は円形としているが、矩形など他の形状でもよい。要は、本発明において所期の機能が得られればよいのである。   As mentioned above, although embodiment of the radioactive waste disposal facility concerning this invention was described, this invention is not limited to said embodiment, In the range which does not deviate from the meaning, it can change suitably. For example, in the above embodiment, the cross section of the radioactive waste disposal facility is circular, but may be other shapes such as a rectangle. In short, it is only necessary to obtain the desired function in the present invention.

本発明に係る放射性廃棄物処分施設の一例を示し、(a)はその側断面図、(b)はA−A矢視断面図である。An example of the radioactive waste disposal facility which concerns on this invention is shown, (a) is the sectional side view, (b) is AA arrow sectional drawing. 本発明に係る放射性廃棄物処分施設の築造方法を示し、(a)(b)(c)は中間部の側断面図、(d)は端部の側断面図である。The construction method of the radioactive waste disposal facility which concerns on this invention is shown, (a) (b) (c) is a sectional side view of an intermediate part, (d) is a sectional side view of an edge part.

符号の説明Explanation of symbols

1、1a、1b、1c 第二改良層(第二改良地盤層)2、2a、2c 第一改良層(第一改良地盤層)3 坑道4 ベントナイト5 放射性廃棄物6 切羽7、7’ 鋼管G 地盤 1, 1a, 1b, 1c Second improvement layer (second improvement ground layer) 2, 2a, 2c First improvement layer ( first improvement ground layer) 3 Tunnel 4 Bentonite 5 Radioactive waste 6 Faces 7, 7 'Steel pipe G ground

Claims (2)

放射性廃棄物を貯蔵するために地盤内に形成された坑道からなる放射性廃棄物処分施設であって、
前記坑道の周壁として形成された地盤がベントナイトグラウトまたは粘土グラウトからなる第一改良地盤層と、当該第一改良地盤層の外周部に形成されたセメント系グラウトまたはシリカ系グラウトからなる第二改良地盤層とを備えることを特徴とする放射性廃棄物処分施設。
A radioactive waste disposal facility consisting of a tunnel formed in the ground for storing radioactive waste,
A first improved ground layer in which the ground formed as a peripheral wall of the mineway is bentonite grout or clay grout, and a second improved ground in which cement ground grout or silica grout is formed on the outer periphery of the first improved ground layer. A radioactive waste disposal facility characterized by comprising a layer.
請求項1に記載の放射性廃棄物処分施設の築造方法であって、
切羽より前方の坑道としての掘削領域を囲繞する前記第二改良地盤層を形成し、次いで前記第二改良地盤層の内方の地盤に前記第一改良地盤層を形成して坑道の周壁となし、その後、前記掘削領域を掘削することを特徴とする放射性廃棄物処分施設の築造方法。
A method for constructing a radioactive waste disposal facility according to claim 1,
Forming the second improved ground layer surrounding the excavation area as a tunnel ahead of the face, and then forming the first improved ground layer on the inner ground of the second improved ground layer to form a peripheral wall of the tunnel Then, the construction method of the radioactive waste disposal facility, wherein the excavation area is excavated.
JP2004223989A 2004-07-30 2004-07-30 Radioactive waste disposal facility and its construction method Expired - Fee Related JP4329076B2 (en)

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RU2315380C1 (en) * 2006-04-10 2008-01-20 Федеральное государственное унитарное предприятие "Научно-исследовательский технологический институт имени А.П. Александрова" Method for case-hardening radioactive waste in container
JP4682944B2 (en) * 2006-07-24 2011-05-11 鹿島建設株式会社 Composite grout water stop method around mine shaft
KR100817616B1 (en) * 2006-10-02 2008-03-31 한국원자력연구원 Buffer blocks for spent fuel and storage systems using them
RU2547812C1 (en) * 2013-10-30 2015-04-10 Федеральное государственное бюджетное учреждение науки Институт физической химиии и электрохимии им. А.Н. Фрумкина Российской академии наук (ИФХЭ РАН) METHOD OF CREATING BARRIER in situ FOR PREVENTING MIGRATION OF COMPONENTS OF RADIOACTIVE WASTES FROM BURIAL AREAS AND RADIOACTIVE CONTAMINATION REGIONS
JP2015129721A (en) * 2014-01-09 2015-07-16 国立大学法人 岡山大学 Radioactive waste disposal facility
RU2704311C2 (en) * 2017-09-12 2019-10-28 Акционерное общество "Центр технологии судостроения и судоремонта" (АО "ЦТСС") Tight sealed container for transportation of package with radioactive wastes (rw) and method of packaging formation and handling in this container
CN113153344B (en) * 2021-04-08 2024-05-28 江苏锐成机械有限公司 High-level waste disposal pit tunneling system for vacuum airtight deslagging

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