JP2017129443A - Storage method and device of radioactive waste - Google Patents

Storage method and device of radioactive waste Download PDF

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JP2017129443A
JP2017129443A JP2016008621A JP2016008621A JP2017129443A JP 2017129443 A JP2017129443 A JP 2017129443A JP 2016008621 A JP2016008621 A JP 2016008621A JP 2016008621 A JP2016008621 A JP 2016008621A JP 2017129443 A JP2017129443 A JP 2017129443A
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radioactive waste
canister
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弘道 前川
Hiromichi Maekawa
弘道 前川
寛明 藤原
Hiroaki Fujiwara
寛明 藤原
翠 内山
Midori Uchiyama
翠 内山
祥太郎 柳田
Shotaro Yanagida
祥太郎 柳田
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IHI Corp
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Abstract

PROBLEM TO BE SOLVED: To provide a storage method and device of radioactive waste capable of keeping low the hydrogen concentration around the radioactive waste.SOLUTION: Radioactive waste 1 is accommodated in a canister 2 having an open structure in a non-seal state. The canister 2 is accommodated and stored in an accommodation tube 3 including: a main tube 7 for accommodating the canister 2; an inlet tube 8 having an inlet pump 11 for supplying ambient air into the main pipe 7; and an outlet tube 9 having an outlet pump 14 for exhausting the air in the main pipe 7 to the outside. In storage, a scavenging process of the accommodation tube 3 is executed, by exhausting the air in the accommodation tube 3 to the outside through the outlet tube 9, and supplying ambient air into the accommodation tube 3 through the inlet tube 8.SELECTED DRAWING: Figure 2

Description

本発明は、放射性廃棄物の貯蔵方法及び装置に関する。   The present invention relates to a radioactive waste storage method and apparatus.

原子力発電所等から排出される燃料デブリ等の放射性廃棄物は、例えば、キャニスタと呼ばれる金属製の容器に収容した状態で、鉄筋コンクリート製の建屋内に貯蔵され、崩壊熱を除くために所定期間にわたり冷却される。   Radioactive waste such as fuel debris discharged from nuclear power plants is stored in a reinforced concrete building in a metal container called a canister, for example, for a predetermined period to eliminate decay heat. To be cooled.

この種の放射性廃棄物の貯蔵方法に関する一般的技術水準を示す文献としては、例えば、下記の特許文献１等がある。   As a document showing a general technical level related to this type of radioactive waste storage method, for example, there is Patent Document 1 below.

特開平１１−２１１８９３号公報JP 11-2111893 A

放射性廃棄物は一般に水冷により一時的な保管を行っている。前記放射性廃棄物を貯蔵する際には、貯蔵に先立って乾燥等の処理を行うが、放射性廃棄物が水分や有機物を含んでいる場合には水素が発生する。特に、燃料デブリには被覆管を構成する素材等が様々な状態で溶け込んでおり、被覆管が溶け込んだ燃料デブリは、長い期間にわたって水素を発生し続ける。燃料デブリは貯蔵のために粉砕を行うが、粉砕した部位によっては水素の発生量が多い部分と少ない部分が存在する。そして、水素の発生量が多い場合には、貯蔵に際して水素濃度を低減する措置を取る必要がある。   In general, radioactive waste is temporarily stored by water cooling. When the radioactive waste is stored, treatment such as drying is performed prior to storage, but hydrogen is generated when the radioactive waste contains moisture or organic matter. In particular, the material constituting the cladding tube is dissolved in various states in the fuel debris, and the fuel debris in which the cladding tube has dissolved continues to generate hydrogen over a long period of time. Fuel debris is pulverized for storage. Depending on the pulverized portion, there are portions where the amount of generated hydrogen is large and portions where the amount of hydrogen is small. When the amount of hydrogen generated is large, it is necessary to take measures to reduce the hydrogen concentration during storage.

本発明は、斯かる実情に鑑み、放射性廃棄物の周囲の水素濃度を低く保ち得る放射性廃棄物の貯蔵方法及び装置を提供しようとするものである。   In view of such circumstances, the present invention intends to provide a radioactive waste storage method and apparatus capable of keeping the hydrogen concentration around the radioactive waste low.

本発明は、
放射性廃棄物を開放構造のキャニスタ内に密封しない状態で収容し、
前記キャニスタを、該キャニスタを収納する主管と、該主管内に外気を給気する入口ポンプを備えた入口管と、前記主管内の気体を外部に排気する出口ポンプを備えた出口管とを備えてなる収納管内に収納して貯蔵し、
貯蔵にあたり、前記収納管内の気体を前記出口管から外部に排気すると共に、外気を前記入口管から前記収納管内に給気することで該収納管の掃気の工程を実行する放射性廃棄物の貯蔵方法にかかるものである。 The present invention
Store radioactive waste in an open structure canister without sealing,
The canister includes a main pipe that houses the canister, an inlet pipe that includes an inlet pump that supplies outside air into the main pipe, and an outlet pipe that includes an outlet pump that exhausts the gas in the main pipe to the outside. Stored in a storage tube,
In storage, a method for storing radioactive waste that exhausts the gas in the storage pipe from the outlet pipe to the outside and supplies the outside air from the inlet pipe to the storage pipe to perform a scavenging process of the storage pipe. It depends on.

本発明の放射性廃棄物の貯蔵方法において、前記出口ポンプは、前記収納管内を陰圧に保つ役割を兼ねることが好ましい。   In the radioactive waste storage method of the present invention, it is preferable that the outlet pump also serves to maintain a negative pressure in the storage pipe.

本発明の放射性廃棄物の貯蔵方法においては、前記収納管内の気体を定期的にサンプリングし、該気体内の水素濃度に応じて前記収納感の掃気の工程を実行することが好ましい。   In the radioactive waste storage method of the present invention, it is preferable to periodically sample the gas in the storage pipe and execute the scavenging process of the storage feeling according to the hydrogen concentration in the gas.

又、本発明は、
放射性廃棄物を密封しない状態で内部に収容する開放構造のキャニスタと、
該キャニスタを内部に収納する主管と、該主管内に外気を給気する入口ポンプを備えた入口管と、前記主管内の気体を外部に排気する出口ポンプを備えた出口管とを備えてなる収納管とを備えた放射性廃棄物の貯蔵装置にかかるものである。 The present invention also provides
An open structure canister that contains radioactive waste in an unsealed state; and
A main pipe that houses the canister; an inlet pipe that includes an inlet pump that supplies outside air into the main pipe; and an outlet pipe that includes an outlet pump that exhausts the gas in the main pipe to the outside. The present invention relates to a radioactive waste storage device including a storage tube.

本発明の放射性廃棄物の貯蔵方法及び装置によれば、放射性廃棄物の周囲の水素濃度を低く保ち得るという優れた効果を奏し得る。   According to the radioactive waste storage method and apparatus of the present invention, it is possible to achieve an excellent effect that the hydrogen concentration around the radioactive waste can be kept low.

本発明の放射性廃棄物の貯蔵方法及び装置の実施例を示す全体概要図である。1 is an overall schematic diagram showing an embodiment of a radioactive waste storage method and apparatus according to the present invention. 本発明の放射性廃棄物の貯蔵方法及び装置の実施例における収納管を示す図である。It is a figure which shows the storage pipe in the Example of the storage method and apparatus of the radioactive waste of this invention. 本発明の放射性廃棄物の貯蔵方法及び装置の実施例におけるキャニスタの内部に配設される中性子吸収材を示す概略図であって、（Ａ）はキャニスタの内壁面を覆うように中性子吸収材を配設した例を示す側断面図及び平断面図、（Ｂ）はキャニスタの内壁面から径方向へ張り出すよう中性子吸収材を配設した例を示す側断面図及び平断面図である。BRIEF DESCRIPTION OF THE DRAWINGS It is the schematic which shows the neutron absorber arrange | positioned inside the canister in the Example of the radioactive waste storage method and apparatus of this invention, Comprising: (A) is a neutron absorber so that the inner wall surface of a canister may be covered. FIG. 4B is a side sectional view and a plan sectional view showing an example in which a neutron absorbing material is disposed so as to project radially from the inner wall surface of the canister. 本発明の放射性廃棄物の貯蔵方法の手順を示すフローチャートである。It is a flowchart which shows the procedure of the storage method of the radioactive waste of this invention.

以下、本発明の実施の形態を添付図面を参照して説明する。   Embodiments of the present invention will be described below with reference to the accompanying drawings.

図１〜図３は本発明の実施による放射性廃棄物の貯蔵方法及び装置の形態の一例を示すものである。本実施例においては、図１に示す如く、放射性廃棄物１を収容したキャニスタ２を収納管３内に上下方向に複数収納し、該収納管３を建屋４内に貯蔵し、該建屋４内に自然通気することで放射性廃棄物１を収容したキャニスタ２ないし収納管３を空冷するようにしている。   1 to 3 show an example of a form of a radioactive waste storage method and apparatus according to an embodiment of the present invention. In the present embodiment, as shown in FIG. 1, a plurality of canisters 2 containing radioactive waste 1 are stored in a storage pipe 3 in the vertical direction, and the storage pipes 3 are stored in a building 4. The canister 2 or the storage tube 3 in which the radioactive waste 1 is stored is air-cooled by natural ventilation.

建屋４は、収納管３の貯蔵部の下方に外部と連通する流路を形成する入口シャフト５、上方に外部と連通する出口シャフト６を備えており、入口シャフト５から外気を取り入れ、出口シャフト６から熱を含んだ空気を排出するようになっている。すなわち、建屋４内の空気は放射性廃棄物１から発生する崩壊熱によって温められて建屋４内の空間を上昇し、出口シャフト６から自然に排気される一方、下方の入口シャフト５からは、出口シャフト６からの排気に伴って温度の低い外気が流入する。入口シャフト５に流入した外気は崩壊熱により温められて上昇し、出口シャフト６から排出される。こうして、キャニスタ２ないし収納管３は、建屋４内における貯蔵の過程で、崩壊熱によって生じる外気のドラフト力により自然空冷されるようになっている。   The building 4 includes an inlet shaft 5 that forms a flow path that communicates with the outside below the storage portion of the storage tube 3, and an outlet shaft 6 that communicates with the outside above the storage pipe 3. The air containing heat is discharged from 6. That is, the air in the building 4 is warmed by the decay heat generated from the radioactive waste 1 and rises in the space in the building 4 and is naturally exhausted from the outlet shaft 6. Ambient air having a low temperature flows in along with the exhaust from the shaft 6. The outside air that has flowed into the inlet shaft 5 is warmed by the decay heat, rises, and is discharged from the outlet shaft 6. Thus, the canister 2 or the storage tube 3 is naturally air-cooled by the draft force of the outside air generated by the decay heat during the storage process in the building 4.

そして、本実施例の場合、各収納管３は、図２に示す如く、キャニスタ２を収納する主管７の下方に入口管８、上方に出口管９を備えており、内部の気体を出口管９から排出すると共に、入口管８から外部の空気を取り入れることで、内部を掃気できるように構成されている。   In the case of this embodiment, as shown in FIG. 2, each storage tube 3 is provided with an inlet tube 8 below the main tube 7 for storing the canister 2 and an outlet tube 9 above, and the gas inside is stored in the outlet tube 3. In addition to exhausting air from the air inlet 9 and taking in external air from the inlet pipe 8, the inside can be scavenged.

入口管８は、プレフィルタとＨＥＰＡフィルタ（High-Efficiency Particulate Air Filter）を有してなる入口フィルタ１０と、該入口フィルタ１０を通して外気を主管７内に引き込む入口ポンプ１１を備えている。又、入口フィルタ１０と入口ポンプ１１の間には逆止弁１２を備えている。   The inlet pipe 8 includes an inlet filter 10 having a prefilter and a HEPA filter (High-Efficiency Particulate Air Filter), and an inlet pump 11 that draws outside air into the main pipe 7 through the inlet filter 10. A check valve 12 is provided between the inlet filter 10 and the inlet pump 11.

同様に、出口管９には、プレフィルタとＨＥＰＡフィルタを有してなる出口フィルタ１３と、該出口フィルタ１３を通して主管７内の気体を外部に排気する出口ポンプ１４を備えている。又、出口管９には、出口ポンプ１４の上流側の位置に逆止弁１５を備え、逆止弁１５と出口ポンプ１４の間に内部の気圧を計測する圧力計１６を備えている。   Similarly, the outlet pipe 9 includes an outlet filter 13 having a pre-filter and a HEPA filter, and an outlet pump 14 that exhausts the gas in the main pipe 7 to the outside through the outlet filter 13. Further, the outlet pipe 9 is provided with a check valve 15 at a position upstream of the outlet pump 14, and a pressure gauge 16 for measuring the internal pressure between the check valve 15 and the outlet pump 14.

主管７は、上部開口７ａからキャニスタ２を上下方向に積み重ねるようにして内部に収納できるようになっており、上部開口７ａは、ガスケット構造を備えた遮蔽プラグ１７で封じることができるようになっている。尚、出口管９は、上部開口７ａからのキャニスタ２の出入りを妨げることのないよう、主管７の側面に備えられている。   The main pipe 7 can be accommodated in the canister 2 by being stacked vertically from the upper opening 7a, and the upper opening 7a can be sealed with a shielding plug 17 having a gasket structure. Yes. The outlet pipe 9 is provided on the side surface of the main pipe 7 so as not to prevent the canister 2 from entering and exiting from the upper opening 7a.

収納管３内に収納されるキャニスタ２は、例えば、図３（Ａ）又は図３（Ｂ）に示す如き構造を備えている。本実施例の場合、キャニスタ２は、燃料デブリ等である放射性廃棄物１を密封しない状態で内部に収容するようになっている。すなわち、キャニスタ２に備えた蓋１８は、放射性廃棄物１をキャニスタ２内に隔離するものであるが、本実施例の蓋１８は、キャニスタ２の気密性を保つガスケットをもたず、漏洩可能な開放構造となっている。このような開放構造のキャニスタ２により、放射性廃棄物１から発生する気体は収納管３内の空間へ逃げることができるようになっている。つまり、本明細書中におけるキャニスタ２を「密封しない状態」とは、キャニスタ２内部から少なくとも気体が漏洩可能な状態を指す。したがって、例えば蓋１８にフィルタを備え、固体の放射性廃棄物１は漏洩しないようキャニスタ２内部に保持しつつ、気体は蓋１８を通して外部に漏出できるように構成しても良い。   The canister 2 stored in the storage tube 3 has a structure as shown in FIG. 3A or FIG. 3B, for example. In the case of the present embodiment, the canister 2 accommodates the radioactive waste 1 such as fuel debris in an unsealed state. That is, the lid 18 provided in the canister 2 is for isolating the radioactive waste 1 in the canister 2, but the lid 18 of this embodiment does not have a gasket that keeps the airtightness of the canister 2 and can leak. Open structure. With such an open canister 2, the gas generated from the radioactive waste 1 can escape to the space in the storage tube 3. That is, the “state in which the canister 2 is not sealed” in this specification refers to a state in which at least gas can leak from the inside of the canister 2. Therefore, for example, the lid 18 may be provided with a filter so that the solid radioactive waste 1 is held inside the canister 2 so as not to leak, and the gas can be leaked to the outside through the lid 18.

蓋１８の内側には、水素と酸素を結合させる再結合触媒１９を備えている。この再結合触媒１９により、水の放射線分解等によってキャニスタ２内に発生した水素を酸素と再結合させて水に戻し、収納管３ないしキャニスタ２内における水素濃度の上昇を極力抑えるようになっている。尚、蓋１８ないしキャニスタ２を開放構造としたことにより、軽い水素がキャニスタ２から選択的に放出される結果、キャニスタ２内部の水素濃度を問題にならないレベルに維持できる場合には、再結合触媒１９は必要ないこともある。   A recombination catalyst 19 that combines hydrogen and oxygen is provided inside the lid 18. By this recombination catalyst 19, hydrogen generated in the canister 2 due to water radiolysis or the like is recombined with oxygen and returned to water, so that an increase in the hydrogen concentration in the storage tube 3 or the canister 2 is suppressed as much as possible. Yes. When the lid 18 or the canister 2 has an open structure, light hydrogen is selectively released from the canister 2 and, as a result, the hydrogen concentration inside the canister 2 can be maintained at a level that does not cause a problem. 19 may not be necessary.

又、キャニスタ２の内部には、中性子吸収材２０を配設してある。中性子吸収材２０は、例えば図３（Ａ）に示す如く、キャニスタ２の内壁面を覆うように配設することができる。又、例えば、図３（Ｂ）に示す如く、キャニスタ２の内壁面から径方向へ張り出し且つキャニスタ２の周方向へ等間隔をあけて配設されるようにしても良い。尚、中性子吸収材２０としては、中性子を吸収する性質をもつ各種の素材を使用できるが、例えば、アルミニウム合金粉末に酸化ホウ素を添加して加熱処理した焼結材を用いることができる。   A neutron absorber 20 is disposed inside the canister 2. The neutron absorber 20 can be disposed so as to cover the inner wall surface of the canister 2, for example, as shown in FIG. Further, for example, as shown in FIG. 3B, the canister 2 may be provided so as to project radially from the inner wall surface and be arranged at equal intervals in the circumferential direction of the canister 2. As the neutron absorber 20, various materials having a property of absorbing neutrons can be used. For example, a sintered material obtained by adding boron oxide to an aluminum alloy powder and performing heat treatment can be used.

次に、上記した本実施例の作動を図４のフローチャートをも参照しながら説明する。   Next, the operation of this embodiment will be described with reference to the flowchart of FIG.

本実施例の放射性廃棄物の貯蔵方法及び装置は、キャニスタ２ないし収納管３の内部を掃気できるようになっており、放射性廃棄物１からの水素の発生量が比較的多い場合に好適である。すなわち、上述の如く燃料デブリ等である放射性廃棄物１の性質はまちまちであり、被覆管の溶け込みによる水素の含有量、あるいは含水量や放射線の発生量その他の条件により、保管中の水素の発生量も異なってくる。ここで、放射性廃棄物１からの水素の発生量が十分に小さいと見込まれる場合には、本発明によらずに、放射性廃棄物１を密封状態で収容することも可能であるが、水素の発生量が比較的多い場合には、放射性廃棄物１を密封しない状態で貯蔵し、発生する水素を掃気によって適宜排出することが、発火を防止するために効果的である。具体的には、空気中の水素濃度が４％以上となると発火の虞があるので、密封して貯蔵することを仮定した際に雰囲気中の水素濃度がその数値に達することが予想される場合には、本実施例の如き貯蔵方法ないし装置により放射性廃棄物１を保管することが望ましい。例えば、貯蔵に先立ち、放射性廃棄物１の一部をサンプリングして放射線を照射し、水素の発生量を確認する試験を行う。その結果、再結合触媒１９の能力等も勘案して、密閉貯蔵すれば空間内の水素濃度が４％に達する可能性があると判断された場合に、本実施例の如きキャニスタ２や収納管３による貯蔵を選択すれば良い。   The radioactive waste storage method and apparatus of the present embodiment can scavenge the inside of the canister 2 or the storage tube 3 and is suitable when the amount of hydrogen generated from the radioactive waste 1 is relatively large. . That is, the nature of the radioactive waste 1 such as fuel debris as described above varies, and the generation of hydrogen during storage depends on the hydrogen content due to the melting of the cladding tube, the water content, the amount of radiation generated, and other conditions. The amount will also vary. Here, when the amount of hydrogen generated from the radioactive waste 1 is expected to be sufficiently small, the radioactive waste 1 can be accommodated in a sealed state regardless of the present invention. When the generation amount is relatively large, it is effective to prevent the ignition by storing the radioactive waste 1 in an unsealed state and appropriately discharging the generated hydrogen by scavenging. Specifically, if the hydrogen concentration in the air is 4% or more, there is a risk of ignition, so it is expected that the hydrogen concentration in the atmosphere will reach that value when assuming sealed storage In this case, it is desirable to store the radioactive waste 1 by a storage method or apparatus as in this embodiment. For example, prior to storage, a test is performed in which a part of the radioactive waste 1 is sampled and irradiated with radiation to check the amount of hydrogen generated. As a result, in consideration of the capacity of the recombination catalyst 19 and the like, if it is determined that there is a possibility that the hydrogen concentration in the space may reach 4% if it is stored tightly, the canister 2 and the storage tube as in this embodiment are used. The storage by 3 may be selected.

貯蔵にあたっては、まずステップＳ１として（図４参照）、放射性廃棄物１を図３（Ａ）や図３（Ｂ）に示す如きキャニスタ２内に収容する。キャニスタ２の開口を密封しないように蓋１８で塞いだ後、ステップＳ２として（図４参照）、図２に示す如く、キャニスタ２を収納管３の主管７に収納し、上部開口７ａを遮蔽プラグ１７で封じる。そして、ステップＳ３として（図４参照）、キャニスタ２を収納した収納管３を、図１に示す如く建屋４内で貯蔵する。   In storage, first, as step S1 (see FIG. 4), the radioactive waste 1 is accommodated in the canister 2 as shown in FIG. 3 (A) or FIG. 3 (B). After closing the opening of the canister 2 with the lid 18 so as not to be sealed, as step S2 (see FIG. 4), as shown in FIG. 2, the canister 2 is stored in the main pipe 7 of the storage pipe 3, and the upper opening 7a is shielded. Seal with 17. And as step S3 (refer FIG. 4), the storage pipe | tube 3 which accommodated the canister 2 is stored in the building 4 as shown in FIG.

貯蔵の間、放射性廃棄物１からは水の放射線分解等により水素が発生する。発生した水素は、ある程度は再結合触媒１９により酸素と結合して水に戻されるが、再結合触媒１９の能力を上回る速度で水素が発生すると、放射性廃棄物１の雰囲気中の水素濃度が上昇していく。キャニスタ２は気体が漏洩可能な状態であるので、発生した水素はキャニスタ２から漏れ出し、収納管３内に徐々に充満していく。   During storage, hydrogen is generated from the radioactive waste 1 by radiolysis of water or the like. The generated hydrogen is combined with oxygen by the recombination catalyst 19 to some extent and returned to water. However, when hydrogen is generated at a rate exceeding the capacity of the recombination catalyst 19, the hydrogen concentration in the atmosphere of the radioactive waste 1 increases. I will do it. Since the canister 2 is in a state where gas can leak, the generated hydrogen leaks from the canister 2 and gradually fills the storage tube 3.

そこで、発火を防止するために、ステップＳ４として収納管３内の水素を排出する（図４参照）。本実施例では、出口ポンプ１４を作動させることにより、収納管３内の気体を出口管９から外部に排気することができる（図２参照）。ここで、水素は軽いために収納管３内で上方に分布しやすく、主管７の上方に備えた出口管９から効率良く排気されていく。この際、出口管９には出口フィルタ１３を備えているため、収納管３内の放射性物質が外部へ漏洩することはない。又、出口ポンプ１４は、放射性物質の封じ込めのため、収納管３内を陰圧に保つ役割をも兼ねている。   Therefore, in order to prevent ignition, hydrogen in the storage tube 3 is discharged as step S4 (see FIG. 4). In the present embodiment, by operating the outlet pump 14, the gas in the storage pipe 3 can be exhausted from the outlet pipe 9 to the outside (see FIG. 2). Here, since hydrogen is light, it tends to be distributed upward in the storage pipe 3 and is efficiently exhausted from the outlet pipe 9 provided above the main pipe 7. At this time, since the outlet pipe 9 includes the outlet filter 13, the radioactive substance in the storage pipe 3 does not leak to the outside. The outlet pump 14 also serves to keep the inside of the storage tube 3 at a negative pressure for containment of radioactive substances.

ここで、収納管３内における水素濃度を低く保つためには、出口管９からの排気だけでは不十分である。このため、本実施例では、ステップＳ４での出口管９からの排気に併せ、ステップＳ５として入口管８から収納管３内に外気を給気し、収納管３内の掃気を行うようにしている（図４参照）。このステップＳ４，Ｓ５からなる掃気の工程により、収納管３内の水素濃度を効果的に低減することができる。   Here, in order to keep the hydrogen concentration in the storage pipe 3 low, exhaust from the outlet pipe 9 alone is not sufficient. For this reason, in this embodiment, in addition to the exhaust from the outlet pipe 9 in step S4, outside air is supplied from the inlet pipe 8 into the storage pipe 3 in step S5, and the storage pipe 3 is scavenged. (See FIG. 4). By the scavenging process including steps S4 and S5, the hydrogen concentration in the storage tube 3 can be effectively reduced.

尚、この掃気の工程において、ステップＳ４とステップＳ５との時間的な関係は特に限定されない。出口管９からの排気を先に実行しても良いし、入口管８からの給気を先に実行しても良い。又、出口管９からの排気と入口管８からの給気を並行して実行することもできる。ここで、いずれにしても、この掃気の工程を通し、収納管３の内部を陰圧に保っておくことが望ましいことは勿論である。   In this scavenging process, the temporal relationship between step S4 and step S5 is not particularly limited. Exhaust from the outlet pipe 9 may be executed first, or air supply from the inlet pipe 8 may be executed first. Also, exhaust from the outlet pipe 9 and supply from the inlet pipe 8 can be performed in parallel. In any case, of course, it is desirable to keep the inside of the storage tube 3 at a negative pressure through this scavenging step.

ステップＳ４，Ｓ５の掃気の工程は、例えば一定期間置きに実行しても良いし、又、収納管３内の気体を定期的にサンプリングし、水素濃度が所定の値まで上昇したことを検知したタイミングで実行しても良い。あるいは、圧力計１６の値が所定値に達したタイミングで実行することもできる。   The scavenging process of steps S4 and S5 may be executed at regular intervals, for example, or the gas in the storage tube 3 is periodically sampled to detect that the hydrogen concentration has increased to a predetermined value. It may be executed at the timing. Alternatively, it can be executed at the timing when the value of the pressure gauge 16 reaches a predetermined value.

上述の如く、建屋４での貯蔵中、キャニスタ２ないし収納管３は、崩壊熱によって生じるドラフト力により自然空冷される（図１参照）。この空冷は、入口シャフト５から取り入れた空気が収納管３の周囲を通過することによって行われ、通過した空気は出口シャフト６から建屋４の外部に排出される。この際、収納管３は主管７の上部開口７ａを遮蔽プラグ１７により封じられ、入口管８と出口管９には入口フィルタ１０と出口フィルタ１３が設置されて気体のみが通過するようになっているので、建屋４内を通過する空気に放射性物質が漏洩することはない。このように、崩壊熱の冷却のための空気の流れと、掃気のための空気の流れは、収納管３の外部と内部とに分離されるようになっている。   As described above, during storage in the building 4, the canister 2 or the storage tube 3 is naturally air-cooled by the draft force generated by the decay heat (see FIG. 1). This air cooling is performed by the air taken in from the inlet shaft 5 passing through the periphery of the storage tube 3, and the passed air is discharged from the outlet shaft 6 to the outside of the building 4. At this time, the storage pipe 3 is sealed with the upper opening 7a of the main pipe 7 by the shielding plug 17, and the inlet pipe 10 and the outlet filter 13 are installed in the inlet pipe 8 and the outlet pipe 9, so that only gas passes therethrough. Therefore, the radioactive substance does not leak into the air passing through the building 4. As described above, the air flow for cooling decay heat and the air flow for scavenging are separated into the outside and the inside of the storage tube 3.

こうして、上記本実施例によれば、放射性廃棄物１の周囲の水素濃度を低く保ち得る。   Thus, according to the present embodiment, the hydrogen concentration around the radioactive waste 1 can be kept low.

又、本実施例では、出口ポンプ１４が収納管３内を陰圧に保つ役割をも兼ねている。このように構成すると、放射性物質を収納管３内に確実に封じ込めることができる。   In the present embodiment, the outlet pump 14 also serves to maintain the inside of the storage tube 3 at a negative pressure. If comprised in this way, a radioactive substance can be reliably enclosed in the storage tube 3. FIG.

更に又、収納管３内の気体を定期的にサンプリングし、該気体内の水素濃度に応じて前記収納管３の掃気の工程を実行するようにすれば、水素濃度の上昇による発火を確実に回避することができる。   Furthermore, if the gas in the storage tube 3 is periodically sampled and the scavenging process of the storage tube 3 is executed according to the hydrogen concentration in the gas, ignition due to an increase in the hydrogen concentration can be ensured. It can be avoided.

尚、本発明の放射性廃棄物の貯蔵方法及び装置は、上述の実施例にのみ限定されるものではなく、本発明の要旨を逸脱しない範囲内において種々変更を加え得ることは勿論である。   In addition, the radioactive waste storage method and apparatus of the present invention are not limited to the above-described embodiments, and various changes can be made without departing from the scope of the present invention.

１ 放射性廃棄物
２ キャニスタ
３ 収納管
７ 主管
８ 入口管
９ 出口管
１１ 入口ポンプ
１４ 出口ポンプ DESCRIPTION OF SYMBOLS 1 Radioactive waste 2 Canister 3 Storage pipe 7 Main pipe 8 Inlet pipe 9 Outlet pipe 11 Inlet pump 14 Outlet pump

Claims (4)

放射性廃棄物を開放構造のキャニスタ内に密封しない状態で収容し、
前記キャニスタを、該キャニスタを収納する主管と、該主管内に外気を給気する入口ポンプを備えた入口管と、前記主管内の気体を外部に排気する出口ポンプを備えた出口管とを備えてなる収納管内に収納して貯蔵し、
貯蔵にあたり、前記収納管内の気体を前記出口管から外部に排気すると共に、外気を前記入口管から前記収納管内に給気することで該収納管の掃気の工程を実行する放射性廃棄物の貯蔵方法。 Store radioactive waste in an open structure canister without sealing,
The canister includes a main pipe that houses the canister, an inlet pipe that includes an inlet pump that supplies outside air into the main pipe, and an outlet pipe that includes an outlet pump that exhausts the gas in the main pipe to the outside. Stored in a storage tube,
In storage, a method for storing radioactive waste that exhausts the gas in the storage pipe from the outlet pipe to the outside and supplies the outside air from the inlet pipe to the storage pipe to perform a scavenging process of the storage pipe. . 前記出口ポンプは、前記収納管内を陰圧に保つ役割を兼ねる請求項１に記載の放射性廃棄物の貯蔵方法。   The method for storing radioactive waste according to claim 1, wherein the outlet pump also serves to maintain a negative pressure in the storage pipe. 前記収納管内の気体を定期的にサンプリングし、該気体内の水素濃度に応じて前記収納管の掃気の工程を実行する請求項１又は２に記載の放射性廃棄物の貯蔵方法。   The radioactive waste storage method according to claim 1 or 2, wherein a gas in the storage pipe is periodically sampled, and a scavenging process of the storage pipe is executed in accordance with a hydrogen concentration in the gas. 放射性廃棄物を密封しない状態で内部に収容する開放構造のキャニスタと、
該キャニスタを内部に収納する主管と、該主管内に外気を給気する入口ポンプを備えた入口管と、前記主管内の気体を外部に排気する出口ポンプを備えた出口管とを備えてなる収納管とを備えた放射性廃棄物の貯蔵装置。 An open structure canister that contains radioactive waste in an unsealed state; and
A main pipe that houses the canister; an inlet pipe that includes an inlet pump that supplies outside air into the main pipe; and an outlet pipe that includes an outlet pump that exhausts the gas in the main pipe to the outside. A radioactive waste storage device comprising a storage tube.
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