JP2001235582A - Cask for dry transport and storage of spent fuel, etc. - Google Patents

Cask for dry transport and storage of spent fuel, etc.

Info

Publication number
JP2001235582A
JP2001235582A JP2000045310A JP2000045310A JP2001235582A JP 2001235582 A JP2001235582 A JP 2001235582A JP 2000045310 A JP2000045310 A JP 2000045310A JP 2000045310 A JP2000045310 A JP 2000045310A JP 2001235582 A JP2001235582 A JP 2001235582A
Authority
JP
Japan
Prior art keywords
container
cask
neutron shielding
shielding material
spent fuel
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.)
Pending
Application number
JP2000045310A
Other languages
Japanese (ja)
Inventor
Sumitora Gonda
純虎 権田
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to JP2000045310A priority Critical patent/JP2001235582A/en
Publication of JP2001235582A publication Critical patent/JP2001235582A/en
Pending legal-status Critical Current

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Classifications

    • 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

Landscapes

  • Particle Accelerators (AREA)

Abstract

PROBLEM TO BE SOLVED: To enhance the capacity removing decay heat from stored spent fuel, improve the neutron shielding capacity, and improve the assemblage by simplifying the structure. SOLUTION: A plurality of shielding body fitting seats 11 are attached to the outer circumferential face of a bottomed cylinder cask 1 with some clearances and a neutron shielding material 4 is provided outside the shielding body fitting seats 11. The outside of the neutron shielding material 4 is covered with a shielding cover 5. A fluid cooling path 12 is formed between the outside of the cask and the shielding cover 5 of the neutron shielding material 4, and cooling fluid 13 flows inside the fluid cooling path 12 from the bottom to the top so as to cool the cask 1. The fluid cooling path 12 prevents the outside face of the cask 1 and the neutron shielding material 4 from directly touching with each other, and the natural convection removes heat from the neutron shielding material 4 so as to prevent it from getting high temperature and eliminate the weight decrease by the long-term heat action, thus preventing the lowering of the neutron shielding capacity.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は、キャスク内に収納
した使用済燃料集合体等からの崩壊熱の除熱能力を高め
た使用済燃料等の乾式輸送,貯蔵用キャスクに関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a cask for dry transportation and storage of spent fuel and the like having an enhanced ability to remove decay heat from spent fuel assemblies and the like stored in a cask.

【0002】[0002]

【従来の技術】原子力発電所の使用済燃料の乾式貯蔵の
形式の一つであるキャスク貯蔵方式は、使用済燃料をし
ゃへい能力を有する容器(キャスク)に収容した状態で
屋外、または建物内に配置しておき、換気を利用して除
熱を行い、放射線しゃへいは重金属やコンクリートの壁
等で行う方式を言う。また、貯蔵専用のキャスクに詰め
替えるのは手間がかかるので、輸送用キャスクをそのま
ま貯蔵用と兼用する方式が開発されている。
2. Description of the Related Art A cask storage system, which is one type of dry storage of spent fuel in a nuclear power plant, is used outdoors or in a building with spent fuel stored in a container (cask) having a shielding ability. It is a method of removing heat using ventilation, and performing radiation shielding on heavy metal or concrete walls. In addition, since it takes time and effort to refill the storage cask, a method has been developed in which the transport cask is also used for storage.

【0003】従来の代表的な乾式輸送,貯蔵用キャスク
を図5及び図6により説明する。図5は乾式輸送,貯蔵
用キャスクを示す縦断面図で、図6は図5におけるA−
A矢視方向に切断した横断面図で、若干拡大して示して
いる。
[0003] A typical conventional cabin for dry transportation and storage will be described with reference to Figs. FIG. 5 is a longitudinal sectional view showing a cask for dry transportation and storage, and FIG.
It is a cross-sectional view cut in the direction of arrow A, and is shown slightly enlarged.

【0004】すなわち、従来の乾式輸送,貯蔵用キャス
クは、使用済燃料の閉じ込めとγ線しゃへいのための鋼
製有底筒状の容器1と、この容器1の上端開口部を閉塞
する鋼製の蓋板2と、前記容器1及び蓋板2を密封する
シール3とボルト18と、前記容器1の外側面と上下両面
の周囲に隙間なく設置された中性子しゃへい用の中性子
しゃへい材4と、この中性子しゃへい材4の外側を覆う
しゃへいカバー5と、前記中性子しゃへい材4を貫通し
て設置された複数の熱放散用伝熱プレート10と、輸送時
の取扱い,貯蔵時の保持のための前記容器の外周面に取
り付けるトラニオン6と、前記容器1内に設置され使用
済燃料集合体8を保持するとともに臨界防止の機能も併
せ持つバスケット7と、からなっている。
That is, a conventional cask for dry transport and storage is a steel bottomed cylindrical container 1 for confining spent fuel and shielding γ-rays, and a steel container for closing an upper end opening of the container 1. A cover plate 2, a seal 3 for sealing the container 1 and the cover plate 2, a bolt 18, a neutron shielding material 4 for neutron shielding which is installed without gaps around the outer surface and upper and lower surfaces of the container 1, A shielding cover 5 for covering the outside of the neutron shielding material 4, a plurality of heat-dissipating heat transfer plates 10 penetrating through the neutron shielding material 4, and a plurality of heat-transfer plates 10 for handling during transportation and holding during storage. The trunnion 6 includes a trunnion 6 attached to the outer peripheral surface of the container, and a basket 7 installed in the container 1 for holding the spent fuel assembly 8 and also having a function of preventing criticality.

【0005】[0005]

【発明が解決しようとする課題】従来の乾式輸送,貯蔵
用キャスクは、使用済燃料集合体自体の過熱防止、バス
ケット7やシール3の材料にアルミニウム等を用いた場
合に生じるクリープ制限、中性子しゃへい材4などの有
機組成材料の耐熱性からの温度制限等のために、使用済
燃料集合体8からの崩壊熱を適切に除熱する必要があ
る。
The conventional cask for dry transportation and storage is designed to prevent overheating of the spent fuel assembly itself, to limit creep and neutron shielding caused when aluminum or the like is used as the material of the basket 7 and the seal 3. It is necessary to appropriately remove the decay heat from the spent fuel assembly 8 in order to limit the temperature from the heat resistance of the organic composition material such as the material 4.

【0006】しかしながら、容器1の外周面や底面を包
囲する中性子しゃへい材4は、容器1の材料である金属
材料に比較して断熱材と同然であり、十分な除熱を阻害
する。そこで、容器1から中性子しゃへい材4の外部へ
直接的に熱伝導除熱を促進するために、中性子しゃへい
材4を貫通して設置される例えば銅製の伝熱プレート10
を容器1の内周面に多数取り付けるか、または、容器1
の外面にも冷却フィン(図示せず)を取り付ける必要が
ある。
However, the neutron shielding material 4 surrounding the outer peripheral surface and the bottom surface of the container 1 is equivalent to a heat insulating material as compared with the metal material which is the material of the container 1, and hinders sufficient heat removal. Then, in order to directly promote heat conduction and heat removal from the container 1 to the outside of the neutron shielding material 4, for example, a copper heat transfer plate 10 installed through the neutron shielding material 4.
Are attached to the inner peripheral surface of the container 1 or the container 1
It is necessary to attach cooling fins (not shown) also to the outer surface of the fin.

【0007】伝熱プレート10や冷却フィンを取り付けた
場合には、構造の複雑化,組立性の悪化などが生じる課
題がある。また、中性子しゃへい材4は伝熱プレート10
からの中性子フラックスの漏れによる中性子しゃへい機
能の低下があり、中性子しゃへい材4の材料として、例
えばシリコンゴム系の高い耐熱性を有する材料などに限
定されるなどの制約条件があり、そのうえ長期にわたる
熱作用による重量減少と、これに伴う中性子しゃへい機
能の低下などの課題がある。
When the heat transfer plate 10 and the cooling fins are attached, there is a problem that the structure becomes complicated and the assembling property is deteriorated. The neutron shielding material 4 is a heat transfer plate 10
The neutron shielding function is reduced due to the leakage of neutron flux from the neutron shielding material 4, and there are restrictions such as that the material of the neutron shielding material 4 is limited to, for example, a silicon rubber-based material having high heat resistance. There are problems such as weight reduction due to the action and the accompanying decrease in the neutron shielding function.

【0008】本発明は、上記課題を解決するためになさ
れたもので、キャスク内に収納する使用済燃料等からの
崩壊熱の除熱能力を高め、中性子しゃへい能力が向上
し、しかも、構造が簡単で、組立性が向上する機能を備
えた使用済燃料等の乾式輸送・貯蔵用キャスクを提供す
ることにある。
SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and has an improved ability to remove decay heat from spent fuel and the like stored in a cask, thereby improving a neutron shielding ability and, furthermore, a structure. An object of the present invention is to provide a cask for dry transportation and storage of spent fuel and the like, which is simple and has a function of improving assemblability.

【0009】[0009]

【課題を解決するための手段】請求項1に係る発明は、
使用済燃料等を閉じ込めるとともに,γ線しゃへい部を
有する鋼製容器と、この容器を密閉する鋼製蓋板と、こ
の蓋板と前記容器を密封するシールとボルトと、前記容
器及び前記蓋板の周囲に設置された中性子しゃへい材
と、前記容器の側面に取り付けたトラニオンと、前記容
器内に設置され、使用済燃料等を保持するとともに,臨
界防止の機能も併せ持つバスケットとを備えた使用済燃
料等の乾式輸送,貯蔵用キャスクにおいて、前記容器と
中性子しゃへい材の間に流体冷却を通流させる流体冷却
パス用の隙間を設けたことを特徴とする。
The invention according to claim 1 is
A steel container for confining spent fuel and the like and having a γ-ray shielding portion, a steel cover plate for sealing the container, a seal and bolt for sealing the cover plate and the container, the container and the cover plate A neutron shielding material installed around the container, a trunnion attached to the side of the container, and a basket installed in the container and holding a spent fuel and the like and also having a function of preventing criticality. In a cask for dry transportation and storage of fuel or the like, a gap for a fluid cooling path for flowing fluid cooling is provided between the container and the neutron shielding material.

【0010】この発明によれば、容器と、この容器の外
周に設置された中性子しゃへい材との間に生じる間隙に
流体冷却パスを設け、冷却流体の出入口となる部位をテ
ーパ、あるいは緩い曲率を有する流路形状とすることに
より、冷却流体の流れを円滑にし、除熱を促進すること
ができる。
According to the present invention, a fluid cooling path is provided in a gap formed between a container and a neutron shielding material provided on the outer periphery of the container, and a portion serving as an inlet / outlet of a cooling fluid is tapered or has a gentle curvature. By having the flow path shape having the above, the flow of the cooling fluid can be made smooth and the heat removal can be promoted.

【0011】また、容器の外周に設置する中性子しゃへ
い材の内外側面、つまり全面にしゃへいカバーを取り付
けることにより、金属に比べ柔らかく傷つきやすい中性
子しゃへい材を保護し、容器への固定や取扱いを容易に
し、火災などの際の延焼を防止することができる。
Further, by installing a shielding cover on the inner and outer surfaces of the neutron shielding material installed on the outer periphery of the container, that is, on the entire surface, the neutron shielding material which is softer and more easily damaged than metal is protected, and fixing and handling on the container are facilitated. It can prevent the spread of fire in the event of fire.

【0012】請求項2に係る発明は、前記容器の外周面
と前記しゃへい材との間に所定の間隙を有して複数のし
ゃへい体取付座を設けてなることを特徴とする。この発
明によれば、しゃへい体取付座容器外面と中性子しゃへ
い材の間に適切な隙間を設けることができるとともに、
高温となる容器と中性子しゃへい材が直接接触するのを
防止することができる。
The invention according to claim 2 is characterized in that a plurality of shielding body mounting seats are provided with a predetermined gap between the outer peripheral surface of the container and the shielding material. According to the present invention, an appropriate gap can be provided between the outer surface of the shielding body mounting seat container and the neutron shielding material,
It is possible to prevent direct contact between the neutron shielding material and the high temperature container.

【0013】請求項3に係る発明は、前記中性子しゃへ
い材の少なくとも一部を可動しゃへい体と固定しゃへい
体とに複数箇所にわたりブロック化し、前記可動しゃへ
い体を可動機構により開閉できるようにしたことを特徴
とする。この発明によれば、輸送や保存の際にキャスク
を横倒しした状態の際の冷却エアの自然対流を促進し、
横倒し状態でも効果的に除熱できる。
[0013] The invention according to claim 3 is that at least a part of the neutron shielding material is divided into a movable shielding body and a fixed shielding body at a plurality of locations so that the movable shielding body can be opened and closed by a movable mechanism. Features. According to the present invention, the natural convection of cooling air is promoted when the cask is lying down during transportation or storage,
Heat can be effectively removed even when lying down.

【0014】請求項4に係る発明は、前記可動しゃへい
体と前記固定しゃへい体の接続部を、放射線ストリーミ
ング防止のためのオフセット構造とし、開時にもオフセ
ットが維持できる構成とすることを特徴とする。
[0014] The invention according to claim 4 is characterized in that the connecting portion between the movable shield and the fixed shield has an offset structure for preventing radiation streaming, and has a structure capable of maintaining the offset even when opened. .

【0015】この発明によれば、中性子しゃへい効果を
損うことなく、横倒し状態でも除熱機能を発揮できる。
また、前記開閉可能な可動しゃへい体と、固定しゃへい
体の接続部のオフセット構造を、テーパ、あるいは緩い
曲率を有する構造の冷却空気流路としたもので、これに
より横倒し状態でも冷却エアの流れを円滑にし、除熱を
促進することができる。
According to the present invention, the heat removal function can be exerted even in the side-down state without impairing the neutron shielding effect.
Also, the movable shield that can be opened and closed, and the offset structure of the connection portion of the fixed shield is a tapered, or a cooling air flow path having a structure with a gentle curvature, thereby allowing the cooling air flow even in a sideways state. It can smooth out and promote heat removal.

【0016】[0016]

【発明の実施の形態】図1及び図2により、使用済燃料
等の乾式輸送,貯蔵用キャスクの第1の実施の形態を説
明する。図1は本実施の形態に係る乾式輸送,貯蔵用キ
ャスクの第1の実施の形態を示す縦断面図、図2は図1
のB−B矢視方向に沿って切断して横断面を示したもの
である。なお、本実施の形態では使用済燃料等として使
用済燃料集合体の例で説明するが、これに限るものでは
ない。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of a cask for dry transportation and storage of spent fuel and the like will be described with reference to FIGS. FIG. 1 is a longitudinal sectional view showing a first embodiment of a cask for dry transportation and storage according to the present embodiment, and FIG.
2 is a cross-sectional view cut along the direction of arrows BB in FIG. In the present embodiment, an example of a spent fuel assembly will be described as spent fuel or the like, but the present invention is not limited to this.

【0017】本実施の形態は、使用済燃料集合体8の閉
じ込めとγ線しゃへいのための機能を備えた鋼製容器1
と、この容器1の上端開口部を覆う鋼製蓋板2と、この
容器1と蓋板2を密封するシール3及びボルト18と、前
記容器1と蓋板2の周囲に設置された中性子しゃへい用
の中性子しゃへい材4,この中性子しゃへい材4の全周
を後述する冷却パス12側の面も含めて覆うしゃへいカバ
ー5と、輸送時の取扱い、貯蔵時の保持のための容器1
の上部外面に取り付けるトラニオン6と、前記容器1内
に設置され、使用済燃料集合体8を保持するとともに臨
界防止の機能も併せ持つバスケット7とを具備し、さら
に、前記容器1と中性子しゃへい材4の間にしゃへい体
取付座11を介して冷却流体13が通流できる流体冷却パス
12を設けている。
In this embodiment, a steel container 1 having a function for confining a spent fuel assembly 8 and shielding γ-rays is provided.
, A steel cover plate 2 covering the upper end opening of the container 1, a seal 3 and a bolt 18 for sealing the container 1 and the cover plate 2, and a neutron shield installed around the container 1 and the cover plate 2. Neutron shielding material 4 for use, a shielding cover 5 covering the entire circumference of the neutron shielding material 4 including a surface on the side of a cooling path 12 described later, and a container 1 for handling during transportation and holding during storage.
A trunnion 6 attached to an upper outer surface of the container 1 and a basket 7 installed in the container 1 and holding a spent fuel assembly 8 and also having a function of preventing criticality. Further, the container 1 and the neutron shielding material 4 are provided. A fluid cooling path through which the cooling fluid 13 can flow through the shield mounting seat 11
12 are provided.

【0018】この流体冷却パス12は、図示しない支持構
造物により容器1が縦型に支持,貯蔵され、図1に示す
ように立設したキャスクの下方に床9が位置している場
合に最も効率よく冷却効果を発揮でき、その出入口流路
にあたる部位はテーパ、あるいは緩い曲率を有する構造
としている。
This fluid cooling path 12 is most suitable when the container 1 is supported and stored vertically by a support structure (not shown), and the floor 9 is located below the upright cask as shown in FIG. The cooling effect can be efficiently exhibited, and the portion corresponding to the entrance / exit flow path has a structure having a taper or a gentle curvature.

【0019】また、中性子しゃへい材4及びしゃへいカ
バー5は図示しないボルト等により容器1及び蓋板2に
固定されていて、内部には伝熱プレート10のような構造
物は不要である。さらに、バスケット7の材料として
は、臨界防止のため、中性子吸収効果が高く、構造材と
しての強度も有するボロン入アルミニウム、またはボロ
ン入ステンレス鋼等を使用する。
Further, the neutron shielding material 4 and the shielding cover 5 are fixed to the container 1 and the cover plate 2 by bolts or the like (not shown), and no structure such as the heat transfer plate 10 is required inside. Further, as a material of the basket 7, a boron-containing aluminum or a boron-containing stainless steel having a high neutron absorption effect and a strength as a structural material is used to prevent criticality.

【0020】次に、本実施の形態に係る使用済燃料集合
体等の乾式輸送・貯蔵用キャスクの作用について説明す
る。図1に示すように、キャスクが縦型で支持,貯蔵さ
れた状態では、最初に使用済燃料集合体8からの崩壊熱
が容器1を介して外部に熱伝導で伝えられてくる。この
ため、容器1の外面の壁温度が上昇し、これに伴い流体
冷却パス12内を通流する冷却流体13も暖められて、外部
の大気との間に密度差を生じ、このため上向きの浮力が
生じる。
Next, the operation of the cask for dry transportation and storage of the spent fuel assembly and the like according to the present embodiment will be described. As shown in FIG. 1, in a state where the cask is supported and stored in a vertical shape, the decay heat from the spent fuel assembly 8 is first transmitted to the outside via the container 1 by heat conduction. As a result, the wall temperature of the outer surface of the container 1 rises, and the cooling fluid 13 flowing through the fluid cooling path 12 is also warmed, causing a density difference between the cooling fluid 13 and the outside atmosphere. Buoyancy occurs.

【0021】この浮力によって流体冷却パス12内の冷却
流体13は流動を開始し、内部からの熱量に応じた流量で
この熱を外部の大気へと放散する。冷却流体13は流体冷
却パス12下端のテーパ、あるいは緩い曲率を有する入口
から流入し、流体冷却パス12上端のテーパ、あるいは緩
い曲率を有する形状の出口から流出する。これによっ
て、内部の崩壊熱は中性子しゃへい材4を直接通ること
なくほとんど除熱され、中性子しゃへい材4の温度を上
げることがない。
Due to the buoyancy, the cooling fluid 13 in the fluid cooling path 12 starts flowing, and dissipates this heat to the outside atmosphere at a flow rate according to the amount of heat from the inside. The cooling fluid 13 flows in from a taper at the lower end of the fluid cooling path 12 or an inlet having a gentle curvature, and flows out from an outlet having a taper at the upper end of the fluid cooling path 12 or a shape having a gentle curvature. As a result, the internal decay heat is almost completely removed without directly passing through the neutron shielding material 4, and the temperature of the neutron shielding material 4 does not increase.

【0022】なお、冷却パス12はその幅に比べ流路の長
さが長いので、煙突効果による除熱効果の向上も期待で
きる。また、中性子しゃへい材4及びしゃへいカバー5
は図示しないボルト等により容器1及び蓋板2に固定さ
れていて、内部には伝熱プレート10のような構造物は一
切不要なので、一体での製作が可能である。
Since the length of the flow path of the cooling path 12 is longer than the width thereof, an improvement in the heat removal effect by the chimney effect can be expected. Further, the neutron shielding material 4 and the shielding cover 5
Is fixed to the container 1 and the cover plate 2 by bolts or the like (not shown), and since no structure such as the heat transfer plate 10 is required inside, it can be manufactured integrally.

【0023】また、容器1と中性子しゃへい材4との間
で、前記冷却流体13の出入口となる部位をテーパ、また
は緩い曲率を有する流路とすることにより、冷却流体の
流れを円滑にして除熱を促進することができる。さら
に、中性子しゃへい材4全体を覆うようにしゃへいカバ
ー5を取り付けることにより、内部の崩壊熱は中性子し
ゃへい材4を直接通ることなく外気中へ放散され、中性
子しゃへい材4の温度を上げることがない。
Further, between the container 1 and the neutron shielding material 4, a portion serving as an inlet / outlet of the cooling fluid 13 is formed as a flow path having a taper or a gentle curvature, so that the flow of the cooling fluid is smoothed and removed. Can promote heat. Further, by attaching the shielding cover 5 so as to cover the entire neutron shielding material 4, the internal decay heat is dissipated into the outside air without directly passing through the neutron shielding material 4, and the temperature of the neutron shielding material 4 does not increase. .

【0024】したがって、除熱効率が良好となり、かつ
中性子しゃへい材4が長期にわたり熱作用を受けた場合
の重量減少と、それに伴う中性子しゃへい機能の低下が
生じないし、中性子しゃへい材4にボロン入ポリエチレ
ンのような耐熱性の低い素材を使うことも可能なので、
材料選択の幅を広げることができる。
Therefore, the heat removal efficiency is improved, the weight of the neutron shielding material 4 is not reduced when the neutron shielding material 4 is subjected to a thermal action for a long time, and the neutron shielding function is not reduced. It is possible to use materials with low heat resistance,
The range of material selection can be expanded.

【0025】また、図6に示した伝熱プレート10のよう
な構造物も不要となるので、中性子しゃへいの構造が簡
単で、一体での製作も可能であり、伝熱プレート10と中
性子しゃへい材4を交互に施工しなくてはならない従来
の構造に比べ組立性が優れる。さらに、中性子しゃへい
材4はしゃへいカバー5で全体が覆われているので、金
属に比べ柔らかく傷つきやすい中性子しゃへい材4を保
護し、容器1への固定や取扱いを容易にし、火災などの
際の延焼を防止することができる。
Further, since a structure such as the heat transfer plate 10 shown in FIG. 6 is not required, the structure of the neutron shield is simple, and the neutron shield can be manufactured integrally. 4 is superior in assemblability to the conventional structure in which 4 must be alternately constructed. Further, since the neutron shielding material 4 is entirely covered with the shielding cover 5, the neutron shielding material 4 which is softer and more easily damaged than metal is protected, and the neutron shielding material 4 can be easily fixed to the container 1 and handled easily. Can be prevented.

【0026】次に、図3(a),(b)及び図4
(a),(b)により本発明に係る使用済燃料集合体等
の乾式輸送・貯蔵用キャスクの第2の実施の形態を説明
する。本実施の形態は、キャスクが輸送時や貯蔵時に横
倒し状態で使用する場合の例で、図3(a)は本実施の
形態に係るキャスクの縦断面図、図3(b)は図3
(a)のC部拡大図、図4(a)は図3(a)のD−D
矢視方向の横断面図、図4(b)は図4(a)のE部拡
大図である。なお、図3及び図4中、図1及び図2と同
一部分には同一符号を付して重複する部分の説明は省略
する。
Next, FIGS. 3A and 3B and FIG.
A second embodiment of a cask for dry transportation and storage of a spent fuel assembly or the like according to the present invention will be described with reference to (a) and (b). This embodiment is an example in which the cask is used in a horizontal state during transportation or storage. FIG. 3A is a longitudinal sectional view of the cask according to the embodiment, and FIG.
FIG. 4A is an enlarged view of a portion C of FIG.
FIG. 4 (b) is an enlarged view of a portion E in FIG. 4 (a). In FIGS. 3 and 4, the same parts as those in FIGS. 1 and 2 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted.

【0027】本実施の形態に係るキャスクの基本構造
は、図1及び図2に示した第1の実施の形態と殆ど同様
であり、縦型で支持,貯蔵される場合には、第1の実施
の形態と同等の除熱機能を奏する。
The basic structure of the cask according to this embodiment is almost the same as that of the first embodiment shown in FIGS. 1 and 2, and when the cask is supported and stored in a vertical type, the first structure is adopted. It has a heat removal function equivalent to that of the embodiment.

【0028】なお、横倒し状態では自然対流による冷却
流体13の流れが、縦型で使用する場合に比べ若干性能が
低下するので、本実施の形態では横倒し状態で上下の位
置にあたる中性子しゃへい材4としゃへいカバー5の一
部を複数箇所にわたり可動しゃへい体14と固定しゃへい
体15とにブロック化して分離する。
In the sideways state, the flow of the cooling fluid 13 due to natural convection is slightly lower in performance than in the case of a vertical type, so in the present embodiment, the neutron shielding material 4 which is in the upside-down position in the sideways state is used. A part of the shielding cover 5 is divided into a movable shielding body 14 and a fixed shielding body 15 at a plurality of locations and separated.

【0029】すなわち、図3(b)及び図4(b)に示
したように、容器1にリンク機構16を取り付け、可動し
ゃへい体14にスライダ17を取り付け、リンク機構16とス
ライダ17により可動しゃへい体14を上下に移動させて開
閉できるようにしたものである。
That is, as shown in FIGS. 3 (b) and 4 (b), the link mechanism 16 is attached to the container 1, the slider 17 is attached to the movable shield 14, and the movable shield is attached by the link mechanism 16 and the slider 17. The body 14 can be opened and closed by moving it up and down.

【0030】次に、本実施の形態の作用を説明する。本
実施の形態では第1の実施の形態で述べた縦型のような
冷却流体の流れを期待することができないので、冷却流
体13が流れることができる流体冷却パスを作る必要があ
り、このために、ブロック化した上下の可動しゃへい体
14を動かして、この部位に冷却流体13の出入口を設け
る。
Next, the operation of the present embodiment will be described. In the present embodiment, since the flow of the cooling fluid as in the vertical type described in the first embodiment cannot be expected, it is necessary to create a fluid cooling path through which the cooling fluid 13 can flow. , Upper and lower movable shields
14 is moved to provide an inlet / outlet for the cooling fluid 13 at this position.

【0031】可動しゃへい体14が開くとリンク機構16が
持ち上がり、可動しゃへい体14とリンク機構16は蟻溝状
のレールで接合部が摺動可能なスライダ17により接続さ
れている。冷却流体13を通流させるには十分な流路を保
持できるが、中性子ストリーミングは防げる程度にオフ
セットな隙間が開いた段階でその位置に固定する。この
状態で、まず使用済燃料集合体8からの崩壊熱が容器1
を介して外部に熱伝導で伝えられてくる。
When the movable shield 14 is opened, the link mechanism 16 is lifted up, and the movable shield 14 and the link mechanism 16 are connected by a dovetail-shaped rail by a slider 17 whose joint can slide. Although a sufficient flow path can be maintained to allow the cooling fluid 13 to flow, neutron streaming is fixed at that position when an offset gap is opened enough to prevent it. In this state, first, the decay heat from the spent fuel assembly 8 is
Is transmitted to the outside through heat conduction.

【0032】このため、容器1の外面の壁温度が上昇
し、これに伴い冷却パス12の内部の流体も暖められて、
外部の大気との間に密度差を生じ、このため上向きの浮
力が生じる。この浮力によって冷却パス12内の冷却流体
13は流動を開始し、内部からの熱量に応じた流量で、こ
の熱を外部の大気へと放散する。
As a result, the wall temperature on the outer surface of the container 1 rises, and the fluid inside the cooling path 12 is warmed accordingly,
This creates a density difference with the outside atmosphere, which results in upward buoyancy. This buoyancy causes the cooling fluid in the cooling path 12
13 starts to flow and dissipates this heat to the outside atmosphere at a flow rate according to the amount of heat from the inside.

【0033】冷却流体13は下部の可動しゃへい体14の開
口部であるテーパ、あるいは緩い曲率を有する入口から
流入し、上部の可動しゃへい体14の開口部であるテー
パ、あるいは緩い曲率を有する出口から流出する。これ
によって、内部の崩壊熱は中性子しゃへい材4をほとん
ど通ることなく除熱され、中性子しゃへい材4の温度を
上げることがない。
The cooling fluid 13 flows in from the tapered opening having the opening of the lower movable shield 14 or an inlet having a gentle curvature, and from the taper which is the opening in the upper movable shielding 14 or the outlet having a gentle curvature. leak. As a result, the internal decay heat is removed almost without passing through the neutron shielding material 4, and the temperature of the neutron shielding material 4 does not increase.

【0034】なお、可動しゃへい体14を開閉する機構
は、特に本実施の形態の構造に限定するものではなく、
ジャッキボルト方式,スペーサ方式など、種々のものが
使用可能である。また、輸送時、ある程度の走行風が期
待できるならば、導風板などを用いて冷却することも可
能である。
The mechanism for opening and closing the movable shield 14 is not particularly limited to the structure of the present embodiment.
Various types such as a jack bolt type and a spacer type can be used. If a certain amount of traveling wind can be expected during transportation, cooling can be performed using a baffle plate or the like.

【0035】第2の実施の形態によれば、容器1の外周
に取り付く中性子しゃへい材4及びしゃへいカバー5の
一部を複数箇所にわたりブロック化し、これをリンク機
構16により開閉できるようにし、開閉可能な可動しゃへ
い体14と固定しゃへい体15の接続部を放射線ストリーミ
ング防止のためのオフセット構造とし、開時にもオフセ
ットが維持できるようにし、このオフセット構造の冷却
流体13の出入口をテーパ、あるいは緩い曲率を有する構
造の冷却空気流路としている。
According to the second embodiment, the neutron shielding material 4 and a part of the shielding cover 5 attached to the outer periphery of the container 1 are divided into a plurality of blocks, which can be opened and closed by the link mechanism 16, and can be opened and closed. The connection between the movable shield 14 and the fixed shield 15 has an offset structure for preventing radiation streaming, so that the offset can be maintained even when it is opened, and the entrance and exit of the cooling fluid 13 of this offset structure are tapered or have a gentle curvature. It has a cooling air passage having a structure having.

【0036】これにより、横倒し状態でも内部の崩壊熱
は中性子しゃへい材4を直接通ることなく外気中へ放散
され、中性子しゃへい材4の温度を上げることがないの
で、除熱効率が良く、かつ中性子しゃへい材4が長期に
わたり熱作用を受けた場合の重量減少と、それに伴う中
性子しゃへい機能の低下が生じることはない。
As a result, even if the neutron shielding material 4 is laid sideways, the internal decay heat is radiated into the outside air without directly passing through the neutron shielding material 4, so that the temperature of the neutron shielding material 4 is not increased, so that the heat removal efficiency is good and the neutron shielding is good. When the material 4 is subjected to thermal action for a long period of time, the weight does not decrease and the neutron shielding function does not decrease.

【0037】また、中性子しゃへい材4にボロン入ポリ
エチレンのような耐熱性の低い素材を使うことも可能な
ので、材料選択の幅が広がり、また、オフセット構造に
よって可動しゃへい体14の開時にも放射線ストリーミン
グを防止し、冷却流体13の流路の確保が可能となる。
Further, since it is possible to use a material having low heat resistance, such as polyethylene containing boron, as the neutron shielding material 4, the range of material selection can be widened, and the radiation structure can be provided even when the movable shielding body 14 is opened by the offset structure. And the flow path of the cooling fluid 13 can be secured.

【0038】[0038]

【発明の効果】本発明によれば、縦置でも、横倒し状態
でも、容器と中性子しゃへい材の間に冷却流体を通流さ
せることができるので、容器内に収納した使用済燃料等
からの崩壊熱の除熱能力を高め、中性子しゃへい能力を
向上し、構造を簡単化して組立性を向上させた乾式輸
送,貯蔵用キャスクを得ることができる。
According to the present invention, the cooling fluid can flow between the container and the neutron shielding material even when the container is placed vertically or in a horizontal position, so that the collapse of the spent fuel or the like stored in the container can be achieved. It is possible to obtain a cask for dry transportation and storage in which the ability to remove heat is enhanced, the neutron shielding ability is improved, the structure is simplified, and the assemblability is improved.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明に係る使用済燃料等の乾式輸送・貯蔵用
キャスクの第1の実施の形態を示す縦断面図。
FIG. 1 is a longitudinal sectional view showing a first embodiment of a cask for dry transportation and storage of spent fuel and the like according to the present invention.

【図2】図1におけるB−B矢視方向を切断して示す横
断面図。
FIG. 2 is a cross-sectional view cut along the direction of arrows BB in FIG.

【図3】(a)は本発明に係る使用済燃料等の乾式輸送
・貯蔵用キャスクの第2の実施の形態を示す縦断面図、
(b)は(a)におけるC部拡大図。
FIG. 3 (a) is a longitudinal sectional view showing a second embodiment of a cask for dry transportation and storage of spent fuel and the like according to the present invention,
(B) is an enlarged view of a portion C in (a).

【図4】(a)は図3におけるD−D矢視方向を切断し
て示す横断面図、(b)は(a)におけるE部拡大図。
4A is a cross-sectional view cut along a direction indicated by an arrow D-D in FIG. 3, and FIG. 4B is an enlarged view of a portion E in FIG.

【図5】従来の使用済燃料等の乾式輸送・貯蔵用キャス
クを示す縦断面図。
FIG. 5 is a longitudinal sectional view showing a conventional cask for dry transportation and storage of spent fuel and the like.

【図6】図5のA−A矢視方向を切断して示す横断面
図。
FIG. 6 is a cross-sectional view cut along the line AA of FIG. 5;

【符号の説明】[Explanation of symbols]

1…容器、2…蓋板、3…シール、4…中性子しゃへい
材、5…しゃへいカバー、6…トラニオン、7…バスケ
ット、8…使用済燃料集合体、9…床、10…伝熱プレー
ト、11…しゃへい体取付座、12…流体冷却パス、13…冷
却流体、14…可動しゃへい体、15…固定しゃへい体、16
…リンク機構、17…スライダ、18…ボルト。
DESCRIPTION OF SYMBOLS 1 ... Container, 2 ... Lid plate, 3 ... Seal, 4 ... Neutron shielding material, 5 ... Shielding cover, 6 ... Trunnion, 7 ... Basket, 8 ... Spent fuel assembly, 9 ... Floor, 10 ... Heat transfer plate, 11 ... shield mounting seat, 12 ... fluid cooling path, 13 ... cooling fluid, 14 ... movable shield, 15 ... fixed shield, 16
... link mechanism, 17 ... slider, 18 ... bolt.

Claims (4)

【特許請求の範囲】[Claims] 【請求項1】 使用済燃料等を閉じ込めるとともにγ線
しゃへい部を有する鋼製容器と、この容器を密閉する鋼
製蓋板と、この蓋板と前記容器を密封するシールとボル
トと、前記容器及び前記蓋板の周囲に設置された中性子
しゃへい材と、前記容器の側面に取り付けたトラニオン
と、前記容器内に設置され、使用済燃料等を保持すると
ともに臨界防止の機能も併せ持つバスケットとを備えた
使用済燃料等の乾式輸送,貯蔵用キャスクにおいて、前
記容器と中性子しゃへい材の間に流体冷却を通流させる
流体冷却パスを設けたことを特徴とする使用済燃料等の
乾式輸送,貯蔵用キャスク。
1. A steel container for confining spent fuel and the like and having a γ-ray shielding portion, a steel cover plate for sealing the container, a seal and a bolt for sealing the cover plate and the container, and the container. And a neutron shielding material installed around the lid plate, a trunnion attached to the side of the container, and a basket installed in the container, which also holds a spent fuel and the like and also has a function of preventing criticality. A cask for dry transportation and storage of spent fuel, etc., characterized in that a fluid cooling path is provided between the container and the neutron shielding material to allow fluid cooling to flow. Cask.
【請求項2】 前記容器の外周面と前記しゃへい材との
間に所定の間隙を有して複数のしゃへい体取付座を設け
てなることを特徴とする請求項1記載の使用済燃料等の
乾式輸送,貯蔵用キャスク。
2. The spent fuel or the like according to claim 1, wherein a plurality of shielding body mounting seats are provided with a predetermined gap between the outer peripheral surface of the container and the shielding material. Cask for dry transport and storage.
【請求項3】 前記中性子しゃへい材の少なくとも一部
を可動しゃへい体と固定しゃへい体とに複数箇所にわた
りブロック化し、前記可動しゃへい体を可動機構により
開閉できるようにしたことを特徴とする請求項1記載の
使用済燃料等の乾式輸送,貯蔵用キャスク。
3. The method according to claim 1, wherein at least a part of the neutron shielding material is divided into a movable shielding body and a fixed shielding body at a plurality of locations, and the movable shielding body can be opened and closed by a movable mechanism. A cask for dry transportation and storage of the used spent fuel, etc.
【請求項4】 前記可動しゃへい体と前記固定しゃへい
体の接続部を、放射線ストリーミング防止のためのオフ
セット構造とし、開時にも前記オフセットが維持できる
構成とすることを特徴とする請求項3記載の使用済燃料
等の乾式輸送,貯蔵用キャスク。
4. The connection according to claim 3, wherein the connection between the movable shield and the fixed shield has an offset structure for preventing radiation streaming, and the offset can be maintained even when the shield is opened. Cask for dry transport and storage of spent fuel.
JP2000045310A 2000-02-23 2000-02-23 Cask for dry transport and storage of spent fuel, etc. Pending JP2001235582A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2000045310A JP2001235582A (en) 2000-02-23 2000-02-23 Cask for dry transport and storage of spent fuel, etc.

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2000045310A JP2001235582A (en) 2000-02-23 2000-02-23 Cask for dry transport and storage of spent fuel, etc.

Publications (1)

Publication Number Publication Date
JP2001235582A true JP2001235582A (en) 2001-08-31

Family

ID=18567916

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2000045310A Pending JP2001235582A (en) 2000-02-23 2000-02-23 Cask for dry transport and storage of spent fuel, etc.

Country Status (1)

Country Link
JP (1) JP2001235582A (en)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009244045A (en) * 2008-03-31 2009-10-22 Japan Atom Power Co Ltd:The Spent fuel container
CN103065696A (en) * 2012-12-21 2013-04-24 清华大学 Spent fuel dry-type storage device
CN104167232A (en) * 2014-08-19 2014-11-26 中兴能源装备有限公司 Dry-type spent fuel storage device
CN105261402A (en) * 2015-09-07 2016-01-20 中广核工程有限公司 Fuel storage tank for nuclear power plant spent fuel dry-type storage
WO2016151094A1 (en) * 2015-03-25 2016-09-29 Tn International Device for supporting packaging for transporting/storing radioactive materials, including a shroud for guiding air for cooling the packaging by natural convection
CN106448783A (en) * 2016-12-12 2017-02-22 深圳中广核工程设计有限公司 Dual-functional spent-fuel storage and transportation metal tank of nuclear power plant
CN107481777A (en) * 2017-07-07 2017-12-15 中国核电工程有限公司 A kind of shielding construction of the nuclear fuel assembly container with heat sinking function

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009244045A (en) * 2008-03-31 2009-10-22 Japan Atom Power Co Ltd:The Spent fuel container
CN103065696A (en) * 2012-12-21 2013-04-24 清华大学 Spent fuel dry-type storage device
CN103065696B (en) * 2012-12-21 2015-07-15 清华大学 Spent fuel dry-type storage device
CN104167232A (en) * 2014-08-19 2014-11-26 中兴能源装备有限公司 Dry-type spent fuel storage device
CN104167232B (en) * 2014-08-19 2017-05-03 中兴能源装备有限公司 Dry-type spent fuel storage device
WO2016151094A1 (en) * 2015-03-25 2016-09-29 Tn International Device for supporting packaging for transporting/storing radioactive materials, including a shroud for guiding air for cooling the packaging by natural convection
FR3034246A1 (en) * 2015-03-25 2016-09-30 Tn Int DEVICE FOR SUPPORTING A TRANSPORT / STORAGE PACKAGING OF RADIOACTIVE MATERIALS, COMPRISING A COOLING AIR GUIDE DENING OF THE PACKAGING BY NATURAL CONVECTION
US10128011B2 (en) 2015-03-25 2018-11-13 Tn International Device for supporting packaging for transporting/storing radioactive materials, including a shroud for guiding air for cooling the packaging by natural convection
CN105261402A (en) * 2015-09-07 2016-01-20 中广核工程有限公司 Fuel storage tank for nuclear power plant spent fuel dry-type storage
CN106448783A (en) * 2016-12-12 2017-02-22 深圳中广核工程设计有限公司 Dual-functional spent-fuel storage and transportation metal tank of nuclear power plant
WO2018108073A1 (en) * 2016-12-12 2018-06-21 深圳中广核工程设计有限公司 Nuclear power plant spent fuel storage and transportation metal tank
CN107481777A (en) * 2017-07-07 2017-12-15 中国核电工程有限公司 A kind of shielding construction of the nuclear fuel assembly container with heat sinking function

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