JP6174347B2 - Container for radioactive material - Google Patents

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JP6174347B2
JP6174347B2 JP2013058288A JP2013058288A JP6174347B2 JP 6174347 B2 JP6174347 B2 JP 6174347B2 JP 2013058288 A JP2013058288 A JP 2013058288A JP 2013058288 A JP2013058288 A JP 2013058288A JP 6174347 B2 JP6174347 B2 JP 6174347B2
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decontamination film
decontamination
film
container
lid
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JP2014182099A (en
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素之 岡野
素之 岡野
飯塚 豊
豊 飯塚
森田 俊哉
俊哉 森田
那月 谷本
那月 谷本
直洋 原
直洋 原
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Sanyu Rec Co Ltd
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    • 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

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Description

本発明は、放射性物質を収納するための収納室を有するコンクリート製の容器に関する。   The present invention relates to a concrete container having a storage chamber for storing a radioactive substance.

下記特許文献1には、外観が略直方体状を成すコンクリート製の容器本体と、容器本体の凹所に収納された固化体(廃棄物を固化材で処理したもの)の上にコンクリートの後打ちによって設けられた蓋とを備える容器が開示されている。   The following Patent Document 1 discloses a concrete container main body having a substantially rectangular parallelepiped shape and a concrete post-coating on a solidified body (waste treated with a solidifying material) stored in a recess of the container main body. And a lid provided with a lid.

前記の如きコンクリート製の容器は放射線遮蔽効果があることが知られていることから、地方自治体にその処分が任されている8000Bq/kgに満たない放射性物質(放射能を帯びた廃棄物やその焼却灰等を指す)を前記の如きコンクリート製の容器に収納して最終処分場に搬送する試みや最終処分場が設置されるまで保管する試みが為されている。   Since concrete containers such as the above are known to have a radiation shielding effect, radioactive materials less than 8000 Bq / kg for which disposal is entrusted to the local government (radioactive waste and its Attempts have been made to store incinerated ash etc. in a concrete container as described above and transport it to a final disposal site, or to store it until the final disposal site is installed.

しかしながら、前記の如きコンクリート製の容器に前記放射性物質を収納すると、収納室の内面、即ち、コンクリートの地肌に放射性物質が除染困難な状態で付着してしまう。要するに、収納されていた放射性物質を取り出した後の容器が放射性物質となってしまうため、該容器を再利用することができない。   However, when the radioactive substance is stored in the concrete container as described above, the radioactive substance adheres to the inner surface of the storage chamber, that is, the concrete surface in a state where it is difficult to decontaminate. In short, since the container after taking out the stored radioactive substance becomes a radioactive substance, the container cannot be reused.

特開平10−297703号公報JP-A-10-297703

本発明の目的は、収納されていた放射性物質を取り出した後も再利用できる放射性物質収納用容器を提供することにある。   An object of the present invention is to provide a radioactive substance storage container that can be reused after the stored radioactive substance is taken out.

前記目的を達成するため、本発明は、放射性物質を収納するための収納室を有するコンクリート製の容器であって、前記収納室の内面が、熱硬化性プラスチックを主成分とした除染膜で覆われ、前記除染膜は、前記収納室の内面を覆う第1除染膜と、前記第1除染膜よりもヤング率が高く該第1除染膜の内面を覆う第2除染膜を含んでいる。 In order to achieve the above object, the present invention provides a concrete container having a storage chamber for storing a radioactive substance, wherein the inner surface of the storage chamber is a decontamination film mainly composed of a thermosetting plastic. The decontamination film is covered with a first decontamination film that covers the inner surface of the storage chamber, and a second decontamination film that has a higher Young's modulus than the first decontamination film and covers the inner surface of the first decontamination film. Is included .

本発明によれば、収納されていた放射性物質を取り出した後も再利用できる放射性物質収納用容器を提供することができる。   ADVANTAGE OF THE INVENTION According to this invention, the radioactive substance storage container which can be reused after taking out the stored radioactive substance can be provided.

本発明の前記目的及び他の目的と、各目的に応じた特徴と効果は、以下の説明と添付図面によって明らかとなる。   The above and other objects of the present invention, and the features and effects according to the respective objects will become apparent from the following description and the accompanying drawings.

図1は本発明を適用した放射性物質収納用容器(第1実施形態)の縦断面図である。FIG. 1 is a longitudinal sectional view of a radioactive substance storage container (first embodiment) to which the present invention is applied. 図2(A)は図1に示した容器本体の上面図、図2(B)は図2(A)のB−B線拡大縦断面図、図2(C)は図2(A)のC−C線拡大縦断面図である。2A is a top view of the container main body shown in FIG. 1, FIG. 2B is an enlarged vertical sectional view taken along line BB in FIG. 2A, and FIG. 2C is FIG. 2A. It is a CC line expanded vertical sectional view. 図3(A)は図1に示した蓋の上面図、図3(B)は図3(A)のB−B線拡大縦断面図、図3(C)は図3(A)のC−C線拡大縦断面図である。3A is a top view of the lid shown in FIG. 1, FIG. 3B is an enlarged vertical sectional view taken along line BB in FIG. 3A, and FIG. 3C is C in FIG. FIG. 図4は本発明を適用した放射性物質収納用容器(第2実施形態)の縦断面図である。FIG. 4 is a longitudinal sectional view of a radioactive substance storage container (second embodiment) to which the present invention is applied. 図5は本発明を適用した放射性物質収納用容器(第3実施形態)の縦断面図である。FIG. 5 is a longitudinal sectional view of a radioactive substance storage container (third embodiment) to which the present invention is applied.

[第1実施形態(図1〜図3)]
図1に示した容器は、コンクリート製の容器本体11(図2を参照)と、コンクリート製の蓋12(図3を参照)とから構成されている
図1及び図2(A)〜図2(C)に示したように、容器本体11は外観が略直方体状を成し、横断面形が略矩形を成す凹所11aを内側に有している。また、凹所11aの内面(4つの内側面及び内底面)、即ち、コンクリートの地肌は、後に詳述する除染膜11bによって覆われている。さらに、容器本体11の内部には、容器本体11の強度を増すための格子状鉄筋11cが埋設されている。
[First Embodiment (FIGS. 1 to 3)]
The container shown in FIG. 1 includes a container body 11 made of concrete (see FIG. 2) and a lid 12 made of concrete (see FIG. 3) .
As shown in FIG. 1 and FIG. 2 (A) to FIG. 2 (C), the container body 11 has a recess 11a on the inside having an outer appearance of a substantially rectangular parallelepiped shape and a transverse cross-sectional shape of a substantially rectangular shape. Yes. Moreover, the inner surface (four inner side surfaces and inner bottom surface) of the recess 11a, that is, the concrete background is covered with a decontamination film 11b described in detail later. Furthermore, a grid-like reinforcing bar 11 c for increasing the strength of the container body 11 is embedded in the container body 11.

加えて、容器本体11の上面には、凹所11aの上面開口を囲むようにシリコーン樹脂等を主成分とする止水パッキン11dが設けられている。また、容器本体11の上面の外周部分には、シリコーン樹脂等を主成分とするコーキング剤13を充填するための段部11eが設けられている。さらに、容器本体11の上面には、ボルト締結用のナット11f(計8個)が埋設されている。さらに、容器本体11の上面の4隅部分には、吊り下げ用の金具11g(計4個)が埋設されている。   In addition, on the upper surface of the container main body 11, a water-stop packing 11d mainly composed of a silicone resin or the like is provided so as to surround the upper surface opening of the recess 11a. Further, a step portion 11 e for filling a caulking agent 13 mainly composed of a silicone resin or the like is provided on the outer peripheral portion of the upper surface of the container body 11. Further, nuts 11f (8 in total) for fastening bolts are embedded in the upper surface of the container body 11. Furthermore, hanging metal fittings 11g (four in total) are embedded in the four corners of the upper surface of the container body 11.

一方、図1及び図3(A)〜図3(C)に示したように、蓋12は外観が略矩形板状を成し、容器本体11の凹所11aの上面開口に嵌り込む略4角錐台状の嵌合部12aを下面中央に有している。また、嵌合部12aの表面(下面と4つの外側面)、即ち、コンクリートの地肌は、後に詳述する除染膜12bによって覆われている。さらに、蓋12の内部には、蓋12の強度を増すための格子状鉄筋12cが埋設されている。   On the other hand, as shown in FIG. 1 and FIGS. 3A to 3C, the lid 12 has a substantially rectangular plate appearance, and is approximately 4 fitted into the upper surface opening of the recess 11 a of the container body 11. A fitting portion 12a having a truncated pyramid shape is provided at the center of the lower surface. Moreover, the surface (lower surface and four outer surfaces) of the fitting part 12a, ie, the concrete surface, is covered with a decontamination film 12b described in detail later. Furthermore, a lattice-like reinforcing bar 12 c for increasing the strength of the lid 12 is embedded in the lid 12.

加えて、蓋12の4隅には、容器本体11の吊り下げ用の金具11g(計4個)を露出させるために、横断面形が略1/4円形を成す切り欠き12dが設けられている。また、蓋12の上面には、容器本体11のナット11f(計8個)に対応して、ボルト挿入用の2段の貫通孔12e(計8個、上段部分の横断面形が略矩形で下段部分の横断面形が略円形)が設けられ、各貫通孔12eの上段部分の底にはステンレス等から成る穴開き板12e1が設けられている。さらに、蓋12の上面には、吊り下げ用の金具12f(計4個)が各々の中心を結ぶ線が略矩形を成すように埋設されている。   In addition, at the four corners of the lid 12, in order to expose the metal fittings 11g for hanging the container main body 11 (a total of four), notches 12d having a substantially circular shape in cross section are provided. Yes. In addition, on the upper surface of the lid 12, corresponding to the nuts 11f (total 8) of the container body 11, two-stage through holes 12e for bolt insertion (total of 8; the cross-sectional shape of the upper portion is substantially rectangular. The bottom section has a substantially circular cross section, and a perforated plate 12e1 made of stainless steel or the like is provided at the bottom of the upper section of each through hole 12e. Further, hanging metal fittings 12f (a total of four) are embedded in the upper surface of the lid 12 so that the lines connecting the respective centers form a substantially rectangular shape.

参考までに容器本体11及び蓋12の寸法例を挙げれば、容器本体11の図2(A)における縦横寸法は略1600mmで図1における縦寸法は略1450mmで厚さは略150mmであり、凹所11aの図2(A)における縦横寸法は略1300mmで図1における縦寸法は略1300mmである。一方、蓋12の図3(A)における縦横寸法は略1600mmで厚さ(嵌合部12aの除く)は略150mmであり、嵌合部12aの厚さは略20mmである。   For example, if the dimensions of the container body 11 and the lid 12 are given, the vertical and horizontal dimensions of the container body 11 in FIG. 2A are approximately 1600 mm, the vertical dimension in FIG. 1 is approximately 1450 mm, and the thickness is approximately 150 mm. 2A is approximately 1300 mm, and the vertical dimension in FIG. 1 is approximately 1300 mm. On the other hand, the vertical and horizontal dimensions of the lid 12 in FIG. 3A are about 1600 mm, the thickness (excluding the fitting portion 12a) is about 150 mm, and the thickness of the fitting portion 12a is about 20 mm.

ここで、容器本体11及び蓋12の主体を成すコンクリートと、容器本体11及び蓋12に設けられた除染膜11b及び除染膜12bについて詳述する。   Here, the concrete which comprises the container main body 11 and the lid | cover 12 and the decontamination film | membrane 11b and the decontamination film | membrane 12b provided in the container main body 11 and the lid | cover 12 are explained in full detail.

容器本体11及び蓋12の主体を成すコンクリートは、周知のコンクリートと同様、セメント、水、粗骨材、細骨材及び混和材料の混合物を養生して硬化させたものである。細骨材には砂が一般的に使用されるが、容器本体11及び蓋12の厚さが例えば150mmに満たない場合には、該細骨材の少なくとも一部としてフェロニッケルスラグや鉛ガラスカレットを用いると放射線遮蔽効果が多少向上する。また、容器本体11及び蓋12の厚さを例えば略200mmとすれば略150mmの場合に比べて放射線遮蔽効果は多少向上するが、該厚さを200mmよりも厚くしても大幅な放射線遮蔽効果は望めない。   The concrete that forms the main body of the container body 11 and the lid 12 is obtained by curing and hardening a mixture of cement, water, coarse aggregate, fine aggregate, and admixture, as well as known concrete. Sand is generally used for the fine aggregate. When the thickness of the container body 11 and the lid 12 is less than 150 mm, for example, ferronickel slag or lead glass cullet is used as at least a part of the fine aggregate. When using, the radiation shielding effect is somewhat improved. Further, if the thickness of the container main body 11 and the lid 12 is about 200 mm, for example, the radiation shielding effect is slightly improved as compared with the case of about 150 mm. However, even if the thickness is made thicker than 200 mm, the radiation shielding effect is significant. Can't hope.

一方、除染膜11b及び除染膜12bは、エポキシ樹脂、ポリウレタン、アクリル樹脂、シリコ−ン樹脂、不飽和ポリエステル、フェノール樹脂、ポリイミド等の熱硬化性プラスチックを主成分としたものであって、その厚さは5〜15mmの範囲内にある。除染膜11b及び除染膜12bを作製するときには、主剤、硬化剤及び特性調整剤等を適宜含有した塗料を準備し、該塗料を凹所11aの内面と嵌合部12の表面に塗布し、これを常温硬化や加熱硬化(焼付け硬化)の手法によって硬化させる。   On the other hand, the decontamination film 11b and the decontamination film 12b are mainly composed of thermosetting plastics such as epoxy resin, polyurethane, acrylic resin, silicone resin, unsaturated polyester, phenol resin, polyimide, Its thickness is in the range of 5-15 mm. When producing the decontamination film 11b and the decontamination film 12b, a paint containing an appropriate amount of a main agent, a curing agent, a property adjusting agent, and the like is prepared, and the paint is applied to the inner surface of the recess 11a and the surface of the fitting portion 12. This is cured by a method of room temperature curing or heat curing (baking curing).

凹所11aの内面と嵌合部12の表面、即ち、コンクリートの地肌が粗いと除染膜11b及び除染膜12bの内面が平滑にならない場合があるため、このような場合には前記塗料にセメントやモルタルを添加したものを最初に塗布して硬化する処理を行うことが望ましい。また、1回の塗料の塗布及び硬化によって除染膜11b及び除染膜12bを作製するとひび割れを生じる場合があるため、このような場合には塗料の塗布及び硬化を複数回に分けて行うことが望ましい。   If the inner surface of the recess 11a and the surface of the fitting portion 12, that is, the concrete surface is rough, the inner surfaces of the decontamination film 11b and the decontamination film 12b may not be smooth. It is desirable to perform a process of first applying a cement or mortar added and curing. In addition, if the decontamination film 11b and the decontamination film 12b are produced by applying and curing the paint once, cracking may occur. In such a case, the application and curing of the paint should be performed in multiple steps. Is desirable.

前記の容器本体11及び蓋12とから構成された容器に放射性物質RMを収納するときには、内面が除染膜11bで覆われた容器本体11の凹所11aに放射性物質RMを直接、或いは、放射性物質RMを袋詰めしたものを入れ、表面が除染膜12bで覆われた嵌合部12aが凹所11aの上面開口に嵌り込むように蓋12を載置する。そして、蓋12の各貫通孔12eに図示省略のボルトをそれぞれ挿入して、各ボルトのネジ部を容器本体11の各ナット11fに締結する。そして、容器本体11と蓋12の境界部分に現れる段部11eにコーキング剤13を充填する。   When the radioactive substance RM is stored in the container composed of the container body 11 and the lid 12, the radioactive substance RM is directly or radioactively provided in the recess 11a of the container body 11 whose inner surface is covered with the decontamination film 11b. A bag packed with the substance RM is put, and the lid 12 is placed so that the fitting portion 12a whose surface is covered with the decontamination film 12b fits into the upper surface opening of the recess 11a. Then, bolts (not shown) are inserted into the through holes 12 e of the lid 12, and the screw portions of the bolts are fastened to the nuts 11 f of the container body 11. Then, the caulking agent 13 is filled in the step portion 11 e that appears at the boundary portion between the container body 11 and the lid 12.

図1に示した容器は、容器本体11の凹所11aの内面(コンクリートの地肌)が除染膜11bで覆われ、且つ、蓋12の嵌合部12aの表面(コンクリートの地肌)が除染膜12bで覆われているため、容器本体11に蓋12を取り付けた状態では、内面の全体が除染膜11b及び除染膜12bで覆われた略直方体状の収納室SR、即ち、水密性及び気密性を有する収納室SRが画成され、該収納室SRに放射性物質RMが収納された状態となる。つまり、収納室SRに収納された放射性物質RMは除染膜11bと除染膜12bに触れるものの、コンクリートの地肌に触れることはない。   In the container shown in FIG. 1, the inner surface (concrete background) of the recess 11a of the container body 11 is covered with the decontamination film 11b, and the surface (concrete background) of the fitting portion 12a of the lid 12 is decontaminated. Since it is covered with the membrane 12b, in the state where the lid 12 is attached to the container main body 11, the substantially rectangular parallelepiped storage chamber SR in which the entire inner surface is covered with the decontamination membrane 11b and the decontamination membrane 12b, that is, watertightness. In addition, a storage chamber SR having airtightness is defined, and the radioactive material RM is stored in the storage chamber SR. That is, the radioactive material RM stored in the storage chamber SR touches the decontamination film 11b and the decontamination film 12b, but does not touch the concrete background.

また、容器本体11の凹所11aの内面(コンクリートの地肌)を覆う除染膜11bと蓋12の嵌合部12aの表面(コンクリートの地肌)を覆う除染膜12bが何れも熱硬化性プラスチックを主成分としたものであるため、収納室SRに収納された放射性物質RMが除染膜11bと除染膜12bに触れて付着しても、コンクリートの地肌に放射性物質RMが付着した場合に比べて該放射性物質RMの除染を効果的に行うことができる。   Further, the decontamination film 11b covering the inner surface (concrete background) of the recess 11a of the container body 11 and the decontamination film 12b covering the surface of the fitting portion 12a (concrete background) of the lid 12 are both thermosetting plastics. If the radioactive material RM stored in the storage room SR adheres to the decontamination film 11b and the decontamination film 12b and adheres to the concrete ground, In comparison, the radioactive substance RM can be effectively decontaminated.

ここで、前記除染に関する試験例を簡単に紹介する。コンクリートの地肌に塩化セシウム溶液(15000Bq/mL)を0.2mL滴下し1週間放置した後にこれを紙ワイパー(日本製紙クレシア社製のキムワイプ(登録商標)、後掲の紙ワイパーもこれと同じ)で2回の拭き取りを実施した場合における実施前後のβ線カウント量(測定器はアロカ社製のTGS−133、測定距離は5cm)は5000と5000(残存率は100%)であり、さらに水を含んだ紙ワイパーで5回の拭き取りを実施した後のβ線カウント量は5000(残存率は100%)であり、さらに1モル/Lの塩酸を含んだ紙ワイパーで3回の拭き取りを実施した後のβ線カウント量は5000(残存率は100%)であった。   Here, a test example related to the decontamination will be briefly introduced. Drop 0.2 mL of cesium chloride solution (15000 Bq / mL) on the concrete surface and leave it for 1 week, then wipe it with a paper wiper (Kimwipe (registered trademark) manufactured by Nippon Paper Crecia Co., Ltd.) The β-ray counts before and after the implementation when wiping was performed twice (measurement is TGS-133 manufactured by Aroka, measurement distance is 5 cm) are 5000 and 5000 (residual rate is 100%), and water Β-ray count after wiping 5 times with a paper wiper containing 100% (residual rate is 100%), and further wiping 3 times with a paper wiper containing 1 mol / L hydrochloric acid After that, the β-ray count amount was 5000 (residual rate was 100%).

一方、コンクリートの地肌にエポキシ樹脂を主成分とした厚さ8mmの除染膜を作製して、該除染膜に塩化セシウム溶液(15000Bq/mL)を0.2mL滴下し1週間放置した後にこれを紙ワイパーで2回の拭き取りを実施した場合における実施前後のβ線カウント量は5000と1000(残存率は20.0%)であり、さらに水を含んだ紙ワイパーで5回の拭き取りを実施した後のβ線カウント量は140であり(残存率は2.8%)、さらに1モル/Lの塩酸を含んだ紙ワイパーで3回の拭き取りを実施した後のβ線カウント量は120(残存率は2.4%)であった。   On the other hand, a 8 mm thick decontamination membrane was prepared on the concrete surface, and 0.2 mL of a cesium chloride solution (15000 Bq / mL) was dropped on the decontamination membrane and allowed to stand for 1 week. When wiping twice with a paper wiper, the β-ray counts before and after the implementation are 5000 and 1000 (remaining rate is 20.0%), and further wiping with a paper wiper containing water 5 times After that, the β ray count amount was 140 (residual rate was 2.8%), and the β ray count amount after wiping three times with a paper wiper containing 1 mol / L hydrochloric acid was 120 ( The residual rate was 2.4%).

他方、コンクリートの地肌にポリウレタンを主成分とした厚さ8mmの除染膜を作製して、該除染膜に塩化セシウム溶液(15000Bq/mL)を0.2mL滴下し1週間放置した後にこれを紙ワイパーで2回の拭き取りを実施した場合における実施前後のβ線カウント量は5000と2800(残存率は56.0%)であり、さらに水を含んだ紙ワイパーで5回の拭き取りを実施した後のβ線カウント量は1000(残存率は20.0%)であり、さらに1モル/Lの塩酸を含んだ紙ワイパーで3回の拭き取りを実施した後のβ線カウント量は580(残存率は11.6%)であった。   On the other hand, a 8 mm thick decontamination film made of polyurethane as a main component was produced on the concrete surface, and 0.2 mL of a cesium chloride solution (15000 Bq / mL) was dropped on the decontamination film and left for 1 week. When wiping twice with a paper wiper, β-ray count amounts before and after the execution were 5000 and 2800 (remaining rate was 56.0%), and further wiping was performed five times with a paper wiper containing water. The subsequent β-ray count was 1000 (residual rate was 20.0%), and the β-ray count after wiping 3 times with a paper wiper containing 1 mol / L hydrochloric acid was 580 (residual The rate was 11.6%).

前述の試験例からも分かるように、収納室SRに収納された放射性物質RMが除染膜11bと除染膜12bに触れて付着しても、コンクリートの地肌に放射性物質RMが付着した場合に比べて該放射性物質RMの除染を比較的簡単な洗浄(例えば水拭きや水噴射等)によって行うことができるし、洗浄を入念に行えば放射性物質RMの残存率を零に近付けることもできる。つまり、図1に示した容器は、収納室SRに収納されていた放射性物質RMを取り出した後、除染膜11b及び除染膜12bに対して洗浄を行うことによってその再利用が十分に図れる。   As can be seen from the above test example, even if the radioactive material RM stored in the storage chamber SR touches and adheres to the decontamination film 11b and the decontamination film 12b, the radioactive material RM adheres to the concrete background. In comparison, decontamination of the radioactive material RM can be performed by relatively simple cleaning (for example, water wiping or water jetting), and if the cleaning is performed carefully, the residual rate of the radioactive material RM can be close to zero. . That is, the container shown in FIG. 1 can be sufficiently reused by cleaning the decontamination film 11b and the decontamination film 12b after taking out the radioactive material RM stored in the storage room SR. .

さらに、容器本体11の凹所11aの内面(コンクリートの地肌)を覆う除染膜11bと蓋12の嵌合部12aの表面(コンクリートの地肌)を覆う除染膜12bが何れも熱硬化性プラスチックを主成分としたものであり、何れもコンクリートに比べて柔軟性があるため、容器に放射性物質RMを収納する際の衝撃を除染膜11bと除染膜12bにより緩和して、容器本体11の凹所11aの内面や蓋12の嵌合部12aの表面にひび割れ等のダメージが生じることを防止できる。しかも、容器本体11の外表面や蓋12の外表面に除染膜11bと除染膜12bに至る亀裂が経時的に生じたとしても、収納室SRの水密性及び気密性を除染膜11bと除染膜12bによって維持できるため、収納室SRに収納した放射性物質RMが容器外に漏出することも防止できる。   Further, the decontamination film 11b covering the inner surface (concrete background) of the recess 11a of the container body 11 and the decontamination film 12b covering the surface of the fitting portion 12a (concrete background) of the lid 12 are both thermosetting plastics. Since both are flexible compared to concrete, the impact when storing the radioactive material RM in the container is mitigated by the decontamination film 11b and the decontamination film 12b, and the container body 11 It is possible to prevent damage such as cracks from occurring on the inner surface of the recess 11a and the surface of the fitting portion 12a of the lid 12. Moreover, even if cracks leading to the decontamination film 11b and the decontamination film 12b occur over time on the outer surface of the container body 11 and the outer surface of the lid 12, the decontamination film 11b maintains the watertightness and airtightness of the storage chamber SR. Therefore, the radioactive material RM stored in the storage chamber SR can be prevented from leaking out of the container.

[第2実施形態(図4)]
図4に示した容器が、図1に示した容器(第1実施形態)と構造を異にするところは、
・容器本体11側の除染膜11bを、収納室11aの内面(コンクリートの地肌)を覆う 第1除染膜11b1と、第1除染膜11b1よりもヤング率が高く該第1除染膜11b 1の内面を覆う第2除染膜11b2によって構成した点
・蓋12側の除染膜12bを、嵌合部12aの表面(コンクリートの地肌)を覆う第1除 染膜12b1と、第1除染膜12b1よりもヤング率が高く該第1除染膜12b1の内 面を覆う第2除染膜12b2によって構成した点
にある。
[Second Embodiment (FIG. 4)]
The container shown in FIG. 4 differs from the container shown in FIG. 1 (first embodiment) in structure.
The first decontamination film 11b1 covering the inner surface (concrete background) of the storage chamber 11a with the decontamination film 11b on the container body 11 side has a higher Young's modulus than the first decontamination film 11b1. The first decontamination film 12b1 covering the surface (concrete background) of the fitting portion 12a is replaced with the first decontamination film 12b on the dot / lid 12 side constituted by the second decontamination film 11b2 covering the inner surface of 11b1. The Young's modulus is higher than that of the decontamination film 12b1, and the second decontamination film 12b2 covers the inner surface of the first decontamination film 12b1.

容器本体11側の第1除染膜11b1及び第2除染膜11b2の材料と、蓋12側の第1除染膜12b1及び第2除染膜12b2の材料は、各々のヤング率を考慮した上で適宜選択できる。例えば、第1除染膜11b1及び第1除染膜12b1をポリウレタンを主成分としたものとし、且つ、第2除染膜11b2及び第2除染膜12b2をエポキシ樹脂を主成分としたものとすれば、容器本体11側の「第1除染膜11b1のヤング率<第2除染膜11b2のヤング率」の条件と、蓋12側の「第1除染膜12b1のヤング率<第2除染膜12b2のヤング率」の条件は満足できる。   The material of the first decontamination film 11b1 and the second decontamination film 11b2 on the container body 11 side, and the material of the first decontamination film 12b1 and the second decontamination film 12b2 on the lid 12 side, consider each Young's modulus. The above can be selected as appropriate. For example, the first decontamination film 11b1 and the first decontamination film 12b1 are mainly composed of polyurethane, and the second decontamination film 11b2 and the second decontamination film 12b2 are mainly composed of an epoxy resin. Then, the condition “the Young's modulus of the first decontamination film 11b1 <the Young's modulus of the second decontamination film 11b2” on the container body 11 side and the “Young's modulus of the first decontamination film 12b1” on the lid 12 side <second. The condition of “Young's modulus of decontamination film 12b2” can be satisfied.

図4に示した容器は、容器本体11の凹所11aの内面(コンクリートの地肌)が2層構造の第1除染膜11b1及び第2除染膜11b2で覆われ、且つ、蓋12の嵌合部12aの表面(コンクリートの地肌)が2層構造の第1除染膜12b1及び第2除染膜12b2で覆われているため、図1に示した容器と同様に、収納室SRに収納された放射性物質RMは第2除染膜11b2と第2除染膜12b2に触れるものの、コンクリートの地肌に触れることはない。   In the container shown in FIG. 4, the inner surface (concrete background) of the recess 11a of the container body 11 is covered with the first decontamination film 11b1 and the second decontamination film 11b2 having a two-layer structure, and the cover 12 is fitted. Since the surface (concrete background) of the joint portion 12a is covered with the first decontamination film 12b1 and the second decontamination film 12b2 having a two-layer structure, it is stored in the storage chamber SR in the same manner as the container shown in FIG. The formed radioactive material RM touches the second decontamination film 11b2 and the second decontamination film 12b2, but does not touch the concrete background.

また、容器本体11の凹所11aの内面(コンクリートの地肌)を覆う第1除染膜11b1及び第2除染膜11b2と蓋12の嵌合部12aの表面(コンクリートの地肌)を覆う第1除染膜12b1及び第2除染膜12b2が何れも熱硬化性プラスチックを主成分としたものであるため、収納室SRに収納された放射性物質RMが第2除染膜11b2と第2除染膜12b2に触れて付着しても、図1に示した容器と同様に、コンクリートの地肌に放射性物質RMが付着した場合に比べて該放射性物質RMの除染を比較的簡単な洗浄(例えば水拭きや水噴射等)によって行うことができるし、洗浄を入念に行えば放射性物質RMの残存率を零に近付けることもできる。つまり、図4に示した容器は、収納室SRに収納されていた放射性物質RMを取り出した後、第2除染膜11b2及び第2除染膜12b2に対して洗浄作業を行うことによってその再利用が十分に図れる。   The first decontamination film 11b1 and the second decontamination film 11b2 that cover the inner surface (concrete background) of the recess 11a of the container body 11 and the surface of the fitting portion 12a of the lid 12 (concrete background) are covered. Since both the decontamination film 12b1 and the second decontamination film 12b2 are mainly composed of a thermosetting plastic, the radioactive material RM stored in the storage chamber SR becomes the second decontamination film 11b2 and the second decontamination film. Even if the membrane 12b2 touches and adheres, as in the case of the container shown in FIG. 1, the radioactive material RM can be decontaminated relatively easily (for example, water) compared to the case where the radioactive material RM adheres to the concrete surface. Wiping, water jet, etc.), and if the cleaning is performed carefully, the residual ratio of the radioactive material RM can be brought close to zero. That is, the container shown in FIG. 4 is removed by cleaning the second decontamination film 11b2 and the second decontamination film 12b2 after taking out the radioactive material RM stored in the storage chamber SR. It can be used sufficiently.

さらに、容器本体11の凹所11aの内面(コンクリートの地肌)を覆う第1除染膜11b1及び第2除染膜11b2と蓋12の嵌合部12aの表面(コンクリートの地肌)を覆う第1除染膜12b1及び第2除染膜12b2が何れも熱硬化性プラスチックを主成分としたものであり、何れもコンクリートに比べて柔軟性があるため、容器に放射性物質RMを収納する際の衝撃を第1除染膜11b1及び第2除染膜11b2と第1除染膜12b1及び第2除染膜12b2により緩和して、容器本体11の凹所11aの内面や蓋12の嵌合部12aの表面にひび割れ等のダメージが生じることを防止できる。しかも、容器本体11の外表面や蓋12の外表面に第1除染膜11b1と第1除染膜12b1に至る亀裂が経時的に生じたとしても、収納室SRの水密性及び気密性を第1除染膜11b1及び第2除染膜11b2と第1除染膜12b1及び第2除染膜12b2によって維持できるため、収納室SRに収納した放射性物質RMが容器外に漏出することも防止できる。   Further, the first decontamination film 11b1 and the second decontamination film 11b2 that cover the inner surface (concrete background) of the recess 11a of the container body 11 and the surface of the fitting portion 12a of the lid 12 (concrete background) are covered. Since both the decontamination film 12b1 and the second decontamination film 12b2 are mainly composed of thermosetting plastic, and both are more flexible than concrete, the impact when the radioactive material RM is stored in the container. Is relaxed by the first decontamination film 11b1, the second decontamination film 11b2, the first decontamination film 12b1 and the second decontamination film 12b2, and the inner surface of the recess 11a of the container body 11 and the fitting portion 12a of the lid 12 It is possible to prevent the occurrence of damage such as cracks on the surface of the film. Moreover, even if cracks reaching the first decontamination film 11b1 and the first decontamination film 12b1 occur over time on the outer surface of the container body 11 and the outer surface of the lid 12, the water tightness and air tightness of the storage chamber SR are maintained. Since it can be maintained by the first decontamination film 11b1, the second decontamination film 11b2, the first decontamination film 12b1 and the second decontamination film 12b2, it is possible to prevent the radioactive material RM stored in the storage chamber SR from leaking out of the container. it can.

さらに、容器本体11側の第1除染膜11b1が第2除染膜11b2よりも柔軟性があり、且つ、蓋12側の第1除染膜12b1が第2除染膜12b2よりも柔軟性があるため、前段落で述べたダメージ発生をより的確に防止できる。   Furthermore, the first decontamination film 11b1 on the container body 11 side is more flexible than the second decontamination film 11b2, and the first decontamination film 12b1 on the lid 12 side is more flexible than the second decontamination film 12b2. Therefore, the occurrence of damage described in the previous paragraph can be prevented more accurately.

[第3実施形態(図5)]
図5に示した容器が、図1に示した容器(第1実施形態)と構造を異にするところは、
・容器本体11の外表面(4つの外側面及び外底面)を、除染膜11bよりもヤング率が 低い第3除染膜11hで覆った点
・蓋12の外表面(4つの外側面及び外上面)を、除染膜12bよりもヤング率が低い第 3除染膜12gで覆った点
にある。
[Third Embodiment (FIG. 5)]
The place where the container shown in FIG. 5 differs in structure from the container (first embodiment) shown in FIG.
The outer surface (four outer surfaces and the outer bottom surface) of the container body 11 is covered with a third decontamination film 11h having a Young's modulus lower than that of the decontamination film 11b. The outer surface of the lid 12 (four outer surfaces and The outer upper surface is covered with a third decontamination film 12g having a Young's modulus lower than that of the decontamination film 12b.

容器本体11側の除染膜11b及び第3除染膜11hの材料と、蓋12側の除染膜12b及び第3除染膜12gの材料は、各々のヤング率を考慮した上で適宜選択できる。例えば、除染膜11b及び除染膜12bをエポキシ樹脂を主成分としたものとし、第3除染膜11hをポリウレタンを主成分としたものとすれば、容器本体11側の「除染膜11b1のヤング率>第3除染膜11b2のヤング率」の条件と、蓋12側の「除染膜12bのヤング率>第3除染膜12gのヤング率」の条件は満足できる。   The material of the decontamination film 11b and the third decontamination film 11h on the container body 11 side and the material of the decontamination film 12b and the third decontamination film 12g on the lid 12 side are appropriately selected in consideration of each Young's modulus. it can. For example, if the decontamination film 11b and the decontamination film 12b are mainly composed of epoxy resin, and the third decontamination film 11h is mainly composed of polyurethane, the “decontamination film 11b1 on the container body 11 side” will be described. The Young's modulus of the third decontamination film 11b2 and the "Young's modulus of the decontamination film 12b> the Young's modulus of the third decontamination film 12g" on the lid 12 side can be satisfied.

図5に示した容器は、容器本体11の凹所11aの内面(コンクリートの地肌)が除染膜11bで覆われ、且つ、蓋12の嵌合部12aの表面(コンクリートの地肌)が除染膜12bで覆われているため、図1に示した容器と同様に、収納室SRに収納された放射性物質RMは除染膜11bと除染膜12bに触れるものの、コンクリートの地肌に触れることはない。   In the container shown in FIG. 5, the inner surface (concrete background) of the recess 11a of the container body 11 is covered with the decontamination film 11b, and the surface of the fitting portion 12a of the lid 12 (concrete background) is decontaminated. Since it is covered with the film 12b, the radioactive material RM stored in the storage room SR touches the decontamination film 11b and the decontamination film 12b as in the case of the container shown in FIG. Absent.

また、容器本体11の凹所11aの内面(コンクリートの地肌)を覆う除染膜11bと蓋12の嵌合部12aの表面(コンクリートの地肌)を覆う除染膜12bが何れも熱硬化性プラスチックを主成分としたものであるため、収納室SRに収納された放射性物質RMが除染膜11bと除染膜12bに触れて付着しても、図1に示した容器と同様に、コンクリートの地肌に放射性物質RMが付着した場合に比べて該放射性物質RMの除染を比較的簡単な洗浄(例えば水拭きや水噴射等)によって行うことができるし、洗浄を入念に行えば放射性物質RMの残存率を零に近付けることもできる。つまり、図5に示した容器は、収納室SRに収納されていた放射性物質RMを取り出した後、除染膜11b及び除染膜12bに対して洗浄作業を行うことによってその再利用が十分に図れる。   Further, the decontamination film 11b covering the inner surface (concrete background) of the recess 11a of the container body 11 and the decontamination film 12b covering the surface of the fitting portion 12a (concrete background) of the lid 12 are both thermosetting plastics. Therefore, even if the radioactive material RM stored in the storage chamber SR touches and adheres to the decontamination membrane 11b and the decontamination membrane 12b, as in the container shown in FIG. Compared to the case where the radioactive substance RM adheres to the ground, the radioactive substance RM can be decontaminated by relatively simple cleaning (for example, water wiping or water jetting). If the cleaning is performed carefully, the radioactive substance RM The survival rate of can be close to zero. That is, the container shown in FIG. 5 is sufficiently reused by performing the cleaning operation on the decontamination film 11b and the decontamination film 12b after taking out the radioactive material RM stored in the storage chamber SR. I can plan.

さらに、容器本体11の凹所11aの内面(コンクリートの地肌)を覆う除染膜11bと蓋12の嵌合部12aの表面(コンクリートの地肌)を覆う除染膜12bが何れも熱硬化性プラスチックを主成分としたものであり、何れもコンクリートに比べて柔軟性があるため、容器に放射性物質RMを収納する際の衝撃を除染膜11bと除染膜12bにより緩和して、容器本体11の凹所11aの内面や蓋12の嵌合部12aの表面にひび割れ等のダメージが生じることを防止できる。しかも、容器本体11の外表面や蓋12の外表面に除染膜11bと除染膜12bに至る亀裂が経時的に生じたとしても、収納室SRの水密性及び気密性を除染膜11bと除染膜12bによって維持できるため、収納室SRに収納した放射性物質RMが容器外に漏出することも防止できる。   Further, the decontamination film 11b covering the inner surface (concrete background) of the recess 11a of the container body 11 and the decontamination film 12b covering the surface of the fitting portion 12a (concrete background) of the lid 12 are both thermosetting plastics. Since both are flexible compared to concrete, the impact when storing the radioactive material RM in the container is mitigated by the decontamination film 11b and the decontamination film 12b, and the container body 11 It is possible to prevent damage such as cracks from occurring on the inner surface of the recess 11a and the surface of the fitting portion 12a of the lid 12. Moreover, even if cracks leading to the decontamination film 11b and the decontamination film 12b occur over time on the outer surface of the container body 11 and the outer surface of the lid 12, the decontamination film 11b maintains the watertightness and airtightness of the storage chamber SR. Therefore, the radioactive material RM stored in the storage chamber SR can be prevented from leaking out of the container.

さらに、容器本体11の外表面が第3除染膜11hで覆われ、且つ、蓋12の外表面が第3除染膜12gで覆われているため、容器本体11の外表面や蓋12の外表面に加わる衝撃を第3除染膜11hと第3除染膜12gにより緩和して、容器本体11の外表面や蓋12の外表面にひび割れ等のダメージが生じることを防止できる。   Furthermore, since the outer surface of the container body 11 is covered with the third decontamination film 11h and the outer surface of the lid 12 is covered with the third decontamination film 12g, the outer surface of the container body 11 and the lid 12 The impact applied to the outer surface can be mitigated by the third decontamination film 11h and the third decontamination film 12g, thereby preventing the outer surface of the container body 11 and the outer surface of the lid 12 from being damaged.

尚、前記の第3除染膜11h及び第3除染膜12gは、図4に示した容器(第2実施形態)にも適用できる。即ち、図4に示した容器本体11の外表面(4つの外側面及び外底面)を第2除染膜11b2よりもヤング率が低い第3除染膜11hで覆い、且つ、蓋12の外表面(4つの外側面及び外上面)を第2除染膜12b2よりもヤング率が低い第3除染膜12gで覆うようにしても良い。   The third decontamination film 11h and the third decontamination film 12g can also be applied to the container (second embodiment) shown in FIG. That is, the outer surface (four outer surfaces and outer bottom surface) of the container main body 11 shown in FIG. 4 is covered with the third decontamination film 11h having a Young's modulus lower than that of the second decontamination film 11b2, and the outside of the lid 12 is covered. The surface (four outer surfaces and outer upper surface) may be covered with a third decontamination film 12g having a Young's modulus lower than that of the second decontamination film 12b2.

11…容器本体、11a…凹所、11b…除染膜、12…蓋、12b…除染膜、SR…収納室、RM…放射性物質、11b1,12b1…第1除染膜、11b2,12b2…第2除染膜、11h,12g…第3除染膜。   DESCRIPTION OF SYMBOLS 11 ... Container body, 11a ... Recess, 11b ... Decontamination membrane, 12 ... Lid, 12b ... Decontamination membrane, SR ... Storage chamber, RM ... Radioactive material, 11b1, 12b1 ... First decontamination membrane, 11b2, 12b2 ... 2nd decontamination membrane, 11h, 12g ... 3rd decontamination membrane.

Claims (2)

放射性物質を収納するための収納室を有するコンクリート製の容器であって、前記収納室の内面が、熱硬化性プラスチックを主成分とした除染膜で覆われ、前記除染膜は、前記収納室の内面を覆う第1除染膜と、前記第1除染膜よりもヤング率が高く該第1除染膜の内面を覆う第2除染膜を含む
ことを特徴とする放射性物質収納用容器。
A concrete container having a storage chamber for storing a radioactive substance, wherein an inner surface of the storage chamber is covered with a decontamination film mainly composed of a thermosetting plastic, and the decontamination film is stored in the storage A first decontamination film that covers the inner surface of the chamber, and a second decontamination film that has a higher Young's modulus than the first decontamination film and covers the inner surface of the first decontamination film ,
A radioactive substance storage container.
前記容器の外表面が、熱硬化性プラスチックを主成分とし前記除染膜又は前記第2除染膜よりもヤング率が低い第3除染膜で覆われている
ことを特徴とする請求項1記載の放射性物質収納用容器。
The outer surface of the container is covered with a third decontamination film whose main component is thermosetting plastic and whose Young's modulus is lower than that of the decontamination film or the second decontamination film .
Radioactive substance storage container according to claim 1 Symbol mounting, characterized in that.
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FR2473213B1 (en) * 1980-01-07 1986-03-21 Ecopo LONG-TERM CONTAINMENT DEVICE FOR RADIOACTIVE OR TOXIC WASTE AND ITS MANUFACTURING METHOD
JPH01138499A (en) * 1987-11-24 1989-05-31 Jgc Corp Container for transportation and disposal of radioactive waste
US5225114A (en) * 1991-09-18 1993-07-06 Chem-Nuclear Systems, Inc. Multipurpose container for low-level radioactive waste
JPH05264793A (en) * 1992-03-18 1993-10-12 Hitachi Ltd Water-impermeable vessel for solidifying radioactive waste
JP2004003873A (en) * 2002-03-29 2004-01-08 Genshiryoku Engineering:Kk Method for repairing and performing preventive maintenance treatment on radioactive material handling facility and the like by high-strength resin
JP4272444B2 (en) * 2003-02-06 2009-06-03 中央理化工業株式会社 Multilayer coating film and method for producing the same
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