JPH0590399U - Radioactive material storage device - Google Patents
Radioactive material storage deviceInfo
- Publication number
- JPH0590399U JPH0590399U JP9049191U JP9049191U JPH0590399U JP H0590399 U JPH0590399 U JP H0590399U JP 9049191 U JP9049191 U JP 9049191U JP 9049191 U JP9049191 U JP 9049191U JP H0590399 U JPH0590399 U JP H0590399U
- Authority
- JP
- Japan
- Prior art keywords
- small spaces
- cylindrical container
- cooling air
- cell chamber
- height
- 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.)
- Withdrawn
Links
- 239000012857 radioactive material Substances 0.000 title description 7
- 238000001816 cooling Methods 0.000 claims abstract description 17
- 239000000941 radioactive substance Substances 0.000 claims abstract description 7
- 238000000638 solvent extraction Methods 0.000 claims 1
- 239000011810 insulating material Substances 0.000 abstract description 6
- 238000010276 construction Methods 0.000 abstract description 3
- 230000000694 effects Effects 0.000 abstract description 2
- 239000002901 radioactive waste Substances 0.000 description 3
- 238000004017 vitrification Methods 0.000 description 3
- 238000010438 heat treatment Methods 0.000 description 2
- 238000009423 ventilation Methods 0.000 description 2
- 230000006866 deterioration Effects 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
Landscapes
- Building Environments (AREA)
Abstract
(57)【要約】
【目的】 断熱材等を設けることなく、多くの放射性物
質を貯蔵する。
【構成】 コンクリート壁により囲まれたセル室20内
に、固化体5を収納する筒状容器4を吊持状態に設ける
とともに、該筒状容器4の高さの途中位置に、その回り
のセル室内空間を上下二つの小空間21,22に区画す
る水平壁23を設け、これら各小空間21,22に、該
小空間毎に冷却空気を流通させる吸気口24,25と排
気口26とを設けた。
【効果】 各小空間21,22内における筒状容器4の
高さがそれぞれ小さくなるので、該筒状容器4から各小
空間21,22への放熱量も小さくなり、冷却空気の温
度上昇を低く抑えることができる。したがって、多くの
放射性物質を貯蔵することができるとともに、セル室構
築物に要求される耐熱温度も低減でき、断熱材等の使用
を削減し得て、建設工数も少なくすることができる。
(57) [Summary] [Purpose] To store a large amount of radioactive substances without providing heat insulating materials. [Structure] In a cell chamber 20 surrounded by a concrete wall, a cylindrical container 4 for accommodating a solidified body 5 is provided in a suspended state, and cells around the cylindrical container 4 are provided at an intermediate position of the height of the cylindrical container 4. A horizontal wall 23 that divides the indoor space into two upper and lower small spaces 21 and 22 is provided, and intake ports 24 and 25 and an exhaust port 26 for circulating cooling air in each of the small spaces 21 and 22 are provided. Provided. [Effect] Since the height of the tubular container 4 in each of the small spaces 21 and 22 becomes smaller, the amount of heat radiated from the tubular container 4 to each of the small spaces 21 and 22 becomes smaller, and the temperature of the cooling air rises. It can be kept low. Therefore, a large amount of radioactive substances can be stored, the heat resistant temperature required for the cell chamber structure can be reduced, the use of heat insulating materials and the like can be reduced, and the number of construction steps can be reduced.
Description
【0001】[0001]
本考案は放射性廃棄物等の放射性物質を冷却空気の自然通風によって冷却しつ つ貯蔵する装置に関する。 The present invention relates to a device for storing radioactive materials such as radioactive waste while cooling them by natural ventilation of cooling air.
【0002】[0002]
一般に、原子力発電プラント等で発生する高レベル廃液等の放射性廃棄物は、 例えばガラス固化処理することによって取り扱い性を向上させることができる。 そして、ガラス固化等の処理がなされた固化体はセルの中で貯蔵することが考え られているが、その貯蔵中に放射性物質の崩壊熱による温度上昇がともなうので 、固化体およびその支持構造物を冷却することが必要であるとともに、放射線の 漏洩対策を十分に講じておく必要がある。 Generally, radioactive waste such as high-level waste liquid generated in a nuclear power plant or the like can be improved in handleability by vitrification treatment, for example. Then, it is considered that the solidified body that has been treated by vitrification etc. is stored in the cell, but since the temperature rise due to the decay heat of the radioactive material is accompanied during the storage, the solidified body and its supporting structure. It is necessary to cool the building and it is necessary to take adequate measures against radiation leakage.
【0003】 従来、このような放射性廃棄物の固化体を貯蔵する装置として、例えば図2に 示すように、コンクリート壁によって囲まれたセル室1の天井スラブ2から、遮 蔽プラグ3によって密閉可能としている複数の筒状容器4を間隔をおいて吊持し て、該筒状容器4の中に固化体5を積み重ね状態に収納する計画がなされている 。この場合、固化体5は長期保管を必要とするため、各筒状容器4の回りを囲む ようにコンクリート構造体6を設けて、セル室1内を上部プレナム部7と下部プ レナム部8とに区画し、両プレナム部7,8の間を筒状容器4の回りのリング状 流路9によって連通した構成とされ、大気に通じる吸気口10から取り入れた冷 却空気を下部プレナム部8からリング状流路9に送り込み、上部プレナム部7か ら排気口11を経由させて放出することにより、いわゆる自然通風によって冷却 することが考えられている。Conventionally, as a device for storing such a solidified product of radioactive waste, as shown in FIG. 2, for example, a ceiling plug slab 2 of a cell chamber 1 surrounded by a concrete wall can be sealed with a shielding plug 3. It is planned that the plurality of cylindrical containers 4 are suspended at intervals and the solidified bodies 5 are stored in the cylindrical containers 4 in a stacked state. In this case, since the solidified body 5 needs to be stored for a long period of time, the concrete structure 6 is provided so as to surround each cylindrical container 4, and the inside of the cell chamber 1 is divided into the upper plenum portion 7 and the lower plenum portion 8. The plenum parts 7 and 8 are connected to each other by a ring-shaped flow passage 9 around the cylindrical container 4, and the cooling air taken in from the intake port 10 leading to the atmosphere is introduced from the lower plenum part 8 into the air. It is considered that cooling is carried out by so-called natural ventilation by sending it into the ring-shaped flow passage 9 and discharging it from the upper plenum portion 7 via the exhaust port 11.
【0004】[0004]
ところで、セル室1内に送り込まれる冷却空気は例えば30℃程度であるが、 リング状流路9を経由する途中で固化体5からの熱によって温度上昇する。例え ば固化体5を9段積みで貯蔵する場合、上部プレナム部7まで冷却空気が到達す ると80℃〜100℃程度にまで上昇することになる。これに対して、セル室1 の壁を構成しているコンクリート壁は、耐熱温度が約65℃であり、このため、 固化体5の積み数を少なくして全体の発熱量を小さくするか、コンクリート壁に 断熱材を貼付する等により、コンクリート壁の熱劣化防止対策が必要になり、放 射性物質の貯蔵量が制限されたり、建設工数がかかる等の問題が生じる。 By the way, the cooling air sent into the cell chamber 1 has a temperature of about 30 ° C., for example, but the temperature thereof rises due to the heat from the solidified body 5 while passing through the ring-shaped channel 9. For example, in the case where the solidified bodies 5 are stored in 9 layers, when the cooling air reaches the upper plenum portion 7, the temperature rises to about 80 ° C to 100 ° C. On the other hand, the concrete wall forming the wall of the cell chamber 1 has a heat-resistant temperature of about 65 ° C. Therefore, the number of solidified bodies 5 stacked is reduced to reduce the total calorific value. By attaching a heat insulating material to the concrete wall, it is necessary to take measures to prevent thermal deterioration of the concrete wall, which causes problems such as limiting the storage amount of radioactive materials and increasing construction man-hours.
【0005】 本考案は、断熱材等を設けることなく、多くの放射性物質を貯蔵することがで きる貯蔵装置の提供を目的とする。An object of the present invention is to provide a storage device capable of storing many radioactive substances without providing a heat insulating material or the like.
【0006】[0006]
本考案は、セル室内に、放射性物質を収納する筒状容器を吊持状態に設けると ともに、該筒状容器の高さの途中位置に、その回りのセル室内空間を上下に複数 の小空間に区画する水平壁を設け、これら各小空間に、該小空間毎に冷却空気を 流通させる吸気口と排気口とを設けたことを特徴とする。 According to the present invention, a cylindrical container for storing a radioactive substance is provided in a suspended state in a cell chamber, and the space around the cell chamber is surrounded by a plurality of small spaces at an intermediate position in the height of the cylindrical container. Is provided with a horizontal wall, and an intake port and an exhaust port for circulating cooling air are provided in each of these small spaces.
【0007】[0007]
本考案の貯蔵装置は、セル室内が筒状容器の高さの途中位置で区画され、その 区画された各小空間にそれぞれ冷却空気が送り込まれるようになっているので、 該冷却空気は、その小空間内のみを流通して、筒状容器の高さの例えば半分に相 当する分から熱を受けることになり、したがって、その温度上昇を低く抑えるこ とができる。一方、筒状容器自体は、各小空間にまたがるようにして設けられる ので、その中の放射性物質の貯蔵量は何ら制限されることはなく、全体の熱は各 小空間に分散して放出されることになる。 In the storage device of the present invention, the cell chamber is partitioned at a midpoint of the height of the cylindrical container, and cooling air is sent to each of the partitioned small spaces. The heat flows from only a small space and corresponds to, for example, half of the height of the cylindrical container, so that the temperature rise can be suppressed to a low level. On the other hand, since the cylindrical container itself is installed so as to straddle each small space, there is no limit to the amount of radioactive material stored therein, and the entire heat is dissipated and dissipated in each small space. Will be.
【0008】[0008]
以下、本考案の貯蔵装置の一実施例について、放射性物質としてガラス固化処 理等がなされた固化体を貯蔵するものの例を図1に基づいて説明する。 この貯蔵装置も、セル室20がコンクリート壁によって囲まれているとともに 、その天井スラブ2から複数の筒状容器4が相互に間隔を明けて吊持され、遮蔽 プラグ3によって密閉可能とされている点は、図2の従来例と同様であるが、筒 状容器4の高さ方向の途中位置、図示例ではセル室1の高さのほぼ半分の位置に 、セル室1内空間を上下二つの小空間21,22に区画する水平壁23が設けら れ、各小空間21,22に別々に冷却空気を流通させるように吸気口24,25 と排気口26とが設けられている点で相違するものである。 An embodiment of the storage device of the present invention will be described below with reference to FIG. 1 for storing a solidified body that has undergone vitrification treatment as a radioactive substance. In this storage device as well, the cell chamber 20 is surrounded by a concrete wall, and a plurality of cylindrical containers 4 are suspended from the ceiling slab 2 at intervals from each other and can be sealed by a shielding plug 3. The points are the same as in the conventional example of FIG. 2, but the inner space of the cell chamber 1 is vertically divided into two parts at a midway position in the height direction of the cylindrical container 4, which is approximately half the height of the cell chamber 1 in the illustrated example. A horizontal wall 23 that divides the two small spaces 21, 22 is provided, and intake ports 24, 25 and an exhaust port 26 are provided so as to separately circulate the cooling air in each of the small spaces 21, 22. It is different.
【0009】 前記水平壁23も天井スラブ2等と同じコンクリート壁によって構成され、該 水平壁23で区画された各小空間21,22には、それぞれ上部プレナム部27 ,28、下部プレナム部29,30及び上下両プレナム部を連通させるリング状 流路31,32が形成され、その下部プレナム部29,30に、並列状態の各入 り口シャフト33,34を経由して前記吸気口24,25が別個に接続されてい る。また、各小空間21,22の上部プレナム部27,28は、一つの出口シャ フト35の上下2箇所に接続されて、該出口シャフト35の上端の排気口26に 連通している。The horizontal wall 23 is also made of the same concrete wall as the ceiling slab 2 and the like, and the small spaces 21 and 22 partitioned by the horizontal wall 23 have upper plenum portions 27 and 28 and lower plenum portions 29 and 29, respectively. 30 and the upper and lower plenum portions are connected to each other to form ring-shaped flow passages 31 and 32, and the lower plenum portions 29 and 30 are connected to the intake ports 24 and 25 via the inlet shafts 33 and 34 in parallel. Are connected separately. The upper plenum portions 27, 28 of the small spaces 21, 22 are connected to the upper and lower portions of one outlet shaft 35 and communicate with the exhaust port 26 at the upper end of the outlet shaft 35.
【0010】 一方、筒状容器4内には固化体5が収納されるのであるが、水平壁23と同じ 高さの位置には、固化体5に代えて非発熱体であるダミー36が収納され、該ダ ミー36を介して固化体5が積み重ねられている。On the other hand, the solidified body 5 is housed in the cylindrical container 4, but a dummy 36, which is a non-heating element, is housed in place of the solidified body 5 at the same height as the horizontal wall 23. Then, the solidified bodies 5 are stacked through the damy 36.
【0011】 このように構成した貯蔵装置において、各吸気口24,25から取り込まれた 冷却空気は、それぞれ入り口シャフト33,34を経由して各小空間21,22 の下部プレナム部29,30に導かれ、筒状容器4回りのリング状流路31,3 2を上昇して上部プレナム部27,28から出口シャフト35を経由して排気口 26から放出される。この場合に、筒状容器4内には、両小空間21,22を区 画する位置の付近に非発熱体であるダミー36が収納されているため、該ダミー 36の下方と上方との間の熱伝達がダミー36によって抑制されて、筒状容器4 の下半分と上半分とがそれぞれの小空間21,22に放熱することになり、これ ら小空間21,22内に送り込まれた冷却空気は、筒状容器4のほぼ半分の高さ の範囲内で該筒状容器4から熱を受けることになる。In the storage device configured as described above, the cooling air taken in from the intake ports 24, 25 is introduced into the lower plenum portions 29, 30 of the small spaces 21, 22 via the inlet shafts 33, 34, respectively. It is guided, rises in the ring-shaped flow paths 31, 32 around the cylindrical container 4, and is discharged from the upper plenum portions 27, 28 through the outlet shaft 35 and the exhaust port 26. In this case, since the dummy 36, which is a non-heating element, is housed in the cylindrical container 4 in the vicinity of the position separating the small spaces 21 and 22, a space between the lower side and the upper side of the dummy 36 is accommodated. The heat transfer of the heat is absorbed by the dummy 36, and the lower half and the upper half of the cylindrical container 4 radiate heat to the small spaces 21 and 22, respectively. The air receives heat from the tubular container 4 within the range of almost half the height of the tubular container 4.
【0012】 したがって、リング状流路31,32を上昇する間の冷却空気への熱伝達量は 筒状容器4全体からの場合のほぼ半分となり、該リング状流路31,32を経由 して上部プレナム部27,28に到達した冷却空気は、その温度上昇が低く抑え られ、該上部プレナム部27,28の雰囲気温度をコンクリート壁の耐熱温度以 下に維持することができる。このため、コンクリート壁に断熱材を貼付する等の 対策は必要なく、コンクリート壁構造のまま放射性物質を有効に長期貯蔵するこ とができる。なお、図示例ではセル室20内を二つに区画したが、要求される温 度特性等に応じて三つ以上に区画してもよい。Therefore, the amount of heat transfer to the cooling air during the ascent of the ring-shaped passages 31 and 32 is almost half that of the case of the entire tubular container 4, and the heat is transferred via the ring-shaped passages 31 and 32. The temperature rise of the cooling air that has reached the upper plenum portions 27, 28 is suppressed to a low level, and the ambient temperature of the upper plenum portions 27, 28 can be maintained below the heat resistant temperature of the concrete wall. Therefore, it is possible to store radioactive materials effectively for a long time without changing the concrete wall structure, such as attaching a heat insulating material to the concrete wall. Although the inside of the cell chamber 20 is divided into two in the illustrated example, it may be divided into three or more depending on the required temperature characteristics and the like.
【0013】[0013]
以上の説明から明らかなように、本考案の貯蔵装置によれば、各小空間内にお ける筒状容器の高さがそれぞれ小さくなるので、該筒状容器から各小空間への放 熱量も小さくなり、冷却空気の温度上昇を低く抑えることができる。したがって 、多くの放射性物質を貯蔵することができるとともに、セル室構築物に要求され る耐熱温度も低減でき、断熱材等の使用を削減し得て、建設工数も少なくするこ とができる等の効果を奏する。 As is clear from the above description, according to the storage device of the present invention, since the height of the tubular container in each small space becomes smaller, the amount of heat released from the tubular container to each small space is also reduced. The size of the cooling air can be reduced, and the temperature rise of the cooling air can be suppressed low. Therefore, it is possible to store a large amount of radioactive material, reduce the heat resistance temperature required for the cell chamber structure, reduce the use of heat insulating materials, and reduce the number of construction steps. Play.
【図1】本考案の貯蔵装置の一実施例を示す縦断面図で
ある。FIG. 1 is a vertical sectional view showing an embodiment of a storage device of the present invention.
【図2】貯蔵装置の従来例を示す縦断面図である。FIG. 2 is a vertical sectional view showing a conventional example of a storage device.
2 天井スラブ 3 遮蔽プラグ 4 筒状容器 5 固化体 6 コンクリート構造体 20 セル室 21,22 小空間 23 水平壁 24,25 吸気口 26 排気口 27,28 上部プレナム部 29,30 下部プレナム部 31,32 リング状流路 33,34 入り口シャフト 35 出口シャフト 36 ダミー 2 Ceiling slab 3 Shielding plug 4 Cylindrical container 5 Solidified body 6 Concrete structure 20 Cell chamber 21, 22 Small space 23 Horizontal wall 24, 25 Inlet port 26 Exhaust port 27, 28 Upper plenum part 29, 30 Lower plenum part 31, 32 ring-shaped channel 33, 34 inlet shaft 35 outlet shaft 36 dummy
Claims (1)
容器を吊持状態に設けるとともに、該筒状容器の高さの
途中位置に、その回りのセル室内空間を上下に複数の小
空間に区画する水平壁を設け、これら各小空間に、該小
空間毎に冷却空気を流通させる吸気口と排気口とを設け
てなる放射性物質の貯蔵装置。1. A cylindrical container for accommodating a radioactive substance is provided in a suspended state in a cell chamber, and a plurality of small spaces are vertically arranged around the tubular container at a midway position of the height of the cylindrical container. A storage device for radioactive substances, which is provided with a horizontal wall for partitioning into, and each of these small spaces is provided with an intake port and an exhaust port through which cooling air flows.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9049191U JPH0590399U (en) | 1991-11-05 | 1991-11-05 | Radioactive material storage device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9049191U JPH0590399U (en) | 1991-11-05 | 1991-11-05 | Radioactive material storage device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0590399U true JPH0590399U (en) | 1993-12-10 |
Family
ID=14000002
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9049191U Withdrawn JPH0590399U (en) | 1991-11-05 | 1991-11-05 | Radioactive material storage device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0590399U (en) |
-
1991
- 1991-11-05 JP JP9049191U patent/JPH0590399U/en not_active Withdrawn
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 19960208 |