JPS6028000Y2 - Transport container for spent nuclear fuel - Google Patents

Transport container for spent nuclear fuel

Info

Publication number
JPS6028000Y2
JPS6028000Y2 JP1978130280U JP13028078U JPS6028000Y2 JP S6028000 Y2 JPS6028000 Y2 JP S6028000Y2 JP 1978130280 U JP1978130280 U JP 1978130280U JP 13028078 U JP13028078 U JP 13028078U JP S6028000 Y2 JPS6028000 Y2 JP S6028000Y2
Authority
JP
Japan
Prior art keywords
nuclear fuel
spent nuclear
container
water
storage space
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.)
Expired
Application number
JP1978130280U
Other languages
Japanese (ja)
Other versions
JPS5547625U (en
Inventor
文之 植原
Original Assignee
三菱重工業株式会社
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 三菱重工業株式会社 filed Critical 三菱重工業株式会社
Priority to JP1978130280U priority Critical patent/JPS6028000Y2/en
Publication of JPS5547625U publication Critical patent/JPS5547625U/ja
Application granted granted Critical
Publication of JPS6028000Y2 publication Critical patent/JPS6028000Y2/en
Expired legal-status Critical Current

Links

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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【考案の詳細な説明】 本考案は、使用済核燃料の輸送容器の改良に関する。[Detailed explanation of the idea] The present invention relates to an improvement in a spent nuclear fuel transport container.

使用済核燃料の輸送容器(以下単にキャスクという。A container for transporting spent nuclear fuel (hereinafter simply referred to as a cask).

)には、その収納空間内に使用済核燃料を流体密に収納
するに当って、水とともに収納する形式のものと、然ら
ざる形式のものとがあり、それぞれ湿式と乾式と呼ばれ
ている。
), when storing spent nuclear fuel in a fluid-tight manner in its storage space, there are two types: one in which it is stored with water, and the other in which it is not, and these are called wet type and dry type respectively. .

これら形式のうち、前者の湿式のものにあっては、使用
済核燃料の周囲に充填された水(冷却水)は、該使用済
核燃料から発生する崩壊熱をキャスク外に発散させるた
めの伝熱および同じく核燃料から発せられる放射熱の遮
蔽の効果がある。
Of these types, in the former wet type, the water (cooling water) filled around the spent nuclear fuel is used to conduct heat to dissipate the decay heat generated from the spent nuclear fuel outside the cask. It also has the effect of shielding radiant heat emitted from nuclear fuel.

湿式のキャスクで輸送される代表的使用済核燃料は、軽
水冷却型原子炉のものである。
The typical spent nuclear fuel transported in wet casks is from light water-cooled nuclear reactors.

使用済軽水炉燃料は、細長い燃料が束ねられ、その両端
に取付又は取扱用の一種の金具が配置されて構成されて
いる。
Spent light water reactor fuel is made up of long and narrow bundles of fuel, with a type of metal fitting for attachment or handling arranged at both ends of the bundle.

放射線と熱は、主として燃料棒から出される。Radiation and heat are primarily emitted by the fuel rods.

一方キャスクには勘定により仮想火災事故にあっても、
十分な密閉性が要求されるが、この事故時にはキャスク
内部は相当な高温に達するので、もし冷却水を収納空間
内に充満するように充填しておくと、火災事故時にはそ
の熱膨張力のため、冷却水は圧縮水となって異状な高圧
になり、これを安全にキャスク内に密閉状態とておくこ
とは、キャスクの強度上困難であるのが普通である。
On the other hand, even if there is a virtual fire accident in the cask,
Sufficient airtightness is required, but in the event of an accident, the inside of the cask would reach a considerable high temperature, so if the storage space is filled with cooling water, its thermal expansion force may cause damage in the event of a fire. The cooling water becomes compressed water and has an abnormally high pressure, and it is usually difficult to keep it safely sealed inside the cask due to the strength of the cask.

従って、通常、湿式キャスクにあっては、冷却水を若干
量の空気とともに収納空間内に充填し、火災事故時の高
温下にあっても、冷却水が圧縮水の状態に達することが
ないように設計されているのが一般的である。
Therefore, in wet casks, cooling water is usually filled in the storage space with a small amount of air to prevent the cooling water from reaching the state of compressed water even under high temperatures during a fire accident. It is generally designed to.

しかしこのような方式によれば、火災事故時に収納空間
内が異状な高圧となってキャスクの外殻が破壊されるの
を防止できるが、その反面、通常の使用済核燃料輸送時
(キャスクは、輸送車輌の上に横積される。
However, although this method prevents the outer shell of the cask from being destroyed due to abnormally high pressure in the storage space in the event of a fire accident, on the other hand, during normal transportation of spent nuclear fuel (the cask It is stacked horizontally on top of the transport vehicle.

)においては、収納空間内の燃料棒上方部は冷却水で充
満されておらず。
), the upper part of the fuel rods in the storage space is not filled with cooling water.

上方に気相の部分が生ずる。A gas phase portion is created above.

従って上述の冷却水による放射線遮蔽の効果は、放射線
が使用済核燃料の燃料棒から出るのでその近くの該気相
となる部分においては期待できず。
Therefore, the above-mentioned effect of radiation shielding by the cooling water cannot be expected in the gaseous portion near the fuel rods of the spent nuclear fuel since the radiation is emitted from the fuel rods.

又冷却用フィンのあるキャスク胴部への伝熱が妨げられ
る。
Also, heat transfer to the cask body where the cooling fins are located is impeded.

そのため遮蔽材料の増厚その他の対策が必要となるとい
う問題点があった。
Therefore, there is a problem in that it is necessary to take measures such as increasing the thickness of the shielding material.

本考案は、上記従来のものの問題点を解決することを目
的として提案されたもので、放射線遮蔽材に囲まれた収
納空間に、使用済核燃料を挿入密封して輸送する筒状容
器内の水充填領域内の頂部及び底部に、減圧された気相
空間を有し、該水充填領域内の水の異状な温度上昇に伴
って容易に破壊される構成の密閉容器をそれぞれ配設し
、更に該筒状容器の胴部外周面に多数のフィンを突設し
てなる使用済核燃料の輸送容器に係るものである。
The present invention was proposed with the aim of solving the above-mentioned problems of the conventional methods. Spent nuclear fuel is inserted into a storage space surrounded by radiation shielding material, and the water inside the cylindrical container is sealed and transported. At the top and bottom of the filling area, a closed container having a reduced pressure gas phase space and configured to be easily destroyed due to an abnormal temperature rise of the water in the water filling area is provided, and further This relates to a container for transporting spent nuclear fuel, which has a large number of fins protruding from the outer peripheral surface of the body of the cylindrical container.

以下、添付図面に示す実施例により、本考案につき具体
的に説明する。
Hereinafter, the present invention will be described in detail with reference to embodiments shown in the accompanying drawings.

同図において1は、筒状をなすキャスクの外殻、2はそ
の蓋で、同着2をキャスク外殻1に図示の如く嵌着固定
することにより該キャスク外殻1内を流体密に密封でき
るようになっている。
In the figure, 1 is a cylindrical outer shell of the cask, and 2 is its lid. By fitting and fixing 2 to the cask outer shell 1 as shown in the figure, the inside of the cask outer shell 1 is sealed fluid-tightly. It is now possible to do so.

そしてそれら部材1,2は銅または銅および鉛等の放射
線遮蔽材で形成されて、放射線遮蔽材を形成している。
The members 1 and 2 are made of a radiation shielding material such as copper or copper and lead to form a radiation shielding material.

3はキャスク外殻1の外周に後述る放熱用フィン4との
間に図示のように形成された空間に充填された中性子遮
蔽水層、4はキャスク外殻1の胴部外周に図示のように
取付けられた放熱用フィン、5はキャスク外殻1内の放
射線遮蔽材で囲まれた収納空間で、同収納空間5内には
、冷却水が充填されるとともに、使用済核燃料を装荷す
るためのバスケット6が組込まれており、該バスケット
6内に使用済核燃料7が装荷されるようになっている。
3 is a neutron shielding water layer filled in the space formed between the outer periphery of the cask outer shell 1 and heat dissipation fins 4, which will be described later, as shown in the figure; A heat dissipation fin 5 attached to the cask shell 1 is a storage space surrounded by radiation shielding material, and the storage space 5 is filled with cooling water and used to load spent nuclear fuel. A basket 6 is incorporated, and spent nuclear fuel 7 is loaded into the basket 6.

8′、8″は内部に減圧された気相空間を有する密閉容
器で、それら密閉容器8′、8″は、上記バスケット6
の長手方向の上部及び下部、すなわち、放射性遮蔽材で
囲まれた収納空間の水充填領域内の頂部及び底部に、そ
れぞれ配設される。
8', 8'' are airtight containers having a reduced pressure gas phase space inside, and these airtight containers 8', 8'' are connected to the basket 6.
are disposed at the upper and lower portions of the storage space in the longitudinal direction, that is, at the top and bottom portions within the water-filled region of the storage space surrounded by the radioactive shielding material.

この場合、密閉容器8′、8″の外周部は、冷却水で覆
われている。
In this case, the outer periphery of the closed containers 8', 8'' is covered with cooling water.

また、それら密閉容器8′、8′内部の気相空間は真空
とされるかまたは減圧された空気で充たされている。
Further, the gas phase space inside the closed containers 8', 8' is evacuated or filled with reduced pressure air.

この密閉容器8′、8″の合計体積(気相空間の広さ)
は、上記収納空間5内の冷却水が通常の使用済核燃料輸
送時の温度から、火災事故時の温度に上昇する間に膨張
する体積に等しく、かつ冷却水の温度または圧力が、通
常の使用済核燃料輸送時のそれを超えて異状に上昇した
ときには、該密閉容器8′、8″は容易に破壊されて、
その密閉性が失なわれるように構成されている。
Total volume of these airtight containers 8' and 8'' (width of gas phase space)
is equal to the volume that the cooling water in the storage space 5 expands while rising from the temperature at the time of normal spent nuclear fuel transportation to the temperature at the time of a fire accident, and the temperature or pressure of the cooling water is equal to the temperature at the time of normal use. If the nuclear fuel rises abnormally beyond that during transportation, the sealed containers 8', 8'' will be easily destroyed,
The structure is such that the airtightness is lost.

例えば該密閉容器8′、8″は、外圧の増大によって容
易に座屈、破壊されるような構造、強度をもつように構
成してもよく、また、一定温度を超えたときは、容易に
溶融するような融点をもつ合金材料によって構成しても
よい。
For example, the airtight containers 8', 8'' may be configured to have a structure and strength that allow them to be easily buckled or destroyed by an increase in external pressure, and may also be configured to have a structure and strength that allows them to be easily buckled or destroyed when a certain temperature is exceeded. It may be made of an alloy material having a melting point such that it melts.

本考案は、かかる構成の密閉容器8′、8″を放射線遮
蔽で密閉されたキャスク内の水充填領域内の頂部及び底
部にそれぞれ配設したことを特徴とするものである。
The present invention is characterized in that the sealed containers 8' and 8'' having such a structure are respectively disposed at the top and bottom of the water-filled region of the cask sealed with radiation shielding.

本考案によるキャスクを使用する場合、使用済核燃料7
をそ収納空間5に組込まれたバスケット6内に装荷して
冷却水とともに密封するに当り、輸送中の温度条件にお
いて、異状に高圧な圧縮水とならない範囲内で、丁度収
納空間5内の容積を満たすような量の冷却水を封入する
When using the cask according to the present invention, spent nuclear fuel 7
When loading the water into the basket 6 built into the storage space 5 and sealing it together with cooling water, the volume of the storage space 5 must be adjusted to within a range that does not result in abnormally high pressure compressed water under the temperature conditions during transportation. Fill in enough cooling water to fill the

従ったて本キャスクによる使用済核燃料の輸送時には、
使用済核燃料の発熱のために冷却水は膨張し、収納空間
5内に充満するが、その圧力はその温度に対する飽和蒸
気圧近辺に止まり、異状な上昇を示すようなことはない
Therefore, when transporting spent nuclear fuel in vertical casks,
The cooling water expands due to the heat generated by the spent nuclear fuel and fills the storage space 5, but its pressure remains close to the saturated vapor pressure at that temperature and does not show any abnormal rise.

従って通常の使用済核燃料輸送時には、密閉容器8′、
8″が破壊されるようなことがない。
Therefore, during normal transportation of spent nuclear fuel, the closed container 8',
8" will not be destroyed.

なお、発電所内の吊下げ移送時に何等かの原因で、底部
の密閉容器8″が破壊されて、収納空間5内の冷却水の
水位が下がったとしても、かかる場合には、使用済核燃
料7は、バスケット6とともに、その自重で収納空間5
内を下方に降下するため、使用済核燃料7の上端部が、
冷却水から露出するようなことがない。
Furthermore, even if the sealed container 8'' at the bottom is destroyed for some reason during suspended transportation within the power plant, and the water level of the cooling water in the storage space 5 drops, in such a case, the spent nuclear fuel 7 together with the basket 6, the storage space 5 is reduced by its own weight.
As the spent nuclear fuel 7 descends downward, the upper end of the spent nuclear fuel 7
No exposure to cooling water.

従って、本キャスクの収納空間5内の気相部分は皆無か
、またはそれに近い状態になるので、冷却水による放熱
および放射線遮蔽効果は、キャスクの全周に及ぶ。
Therefore, there is no gas phase in the storage space 5 of the cask, or there is almost no gas phase, so that the heat dissipation and radiation shielding effects of the cooling water extend to the entire circumference of the cask.

一方、発電所外の道路外を輸送するに際腰本キャスクが
火災事故に遭遇したときには、当然冷却水の温度および
圧力が上昇するので気相空間をもつ密閉容器8′、8″
は破壊される。
On the other hand, if the Koshimoto cask encounters a fire accident while being transported off-road outside the power plant, the temperature and pressure of the cooling water will naturally rise, resulting in an airtight container 8', 8'' with a gas phase space.
will be destroyed.

従って収納空間5内の冷却水の占める容積は密閉容器8
′。
Therefore, the volume occupied by the cooling water in the storage space 5 is the volume occupied by the airtight container 8.
'.

8″の体積分だけ増加したことととなるため、該密閉容
器8′、8″の体積を適当に設定することにより、冷却
水は火災事故の最高温度に達して相当に膨張しても、異
常に高圧な圧縮水となるようなことはなくキャスク外殻
の耐圧強度は、上記最高温度に対する飽和蒸気圧に近い
もので十分である。
Therefore, by appropriately setting the volume of the sealed containers 8' and 8'', even if the cooling water reaches the maximum temperature at which a fire occurs and expands considerably, There is no case of abnormally high pressure compressed water, and the pressure resistance of the cask shell is sufficient to be close to the saturated vapor pressure at the maximum temperature.

また、上記密閉容器8′、8″の内部は、真空にされる
か、または減圧した空気で満たされているため、その内
部に大気圧の空気を封入した場合に比し、火災事故時に
おける冷却水の圧力上昇をより低くすることができる利
点がある。
In addition, since the inside of the airtight containers 8', 8'' is evacuated or filled with reduced pressure air, compared to the case where air at atmospheric pressure is sealed inside, the airtight container 8', 8'' This has the advantage of lowering the pressure rise of the cooling water.

本考案の使用済核燃料の輸送容器は、上記のような構成
、作用を具有するものであるから、本考案によれば、上
記従来の問題点をすべて解決腰使用済核燃料の通常の道
路輸送時にあっては、輸送容器の収納空間5内の気相部
分は皆無か、あるいはそれに近い極少量の状態となるた
め、使用済核燃料の燃料棒部から出る熱は、フィンのあ
る胴部へ冷却水を介して伝えられ、放熱は好適に行なわ
れる。
Since the spent nuclear fuel transport container of the present invention has the above-mentioned structure and function, the present invention solves all the above-mentioned conventional problems. If so, the gas phase inside the storage space 5 of the transport container will be non-existent, or there will be a very small amount close to it, so the heat emitted from the fuel rods of the spent nuclear fuel is transferred to the finned body by cooling water. The heat is transmitted through, and the heat is dissipated appropriately.

また、燃料棒部から半径方向へ出る放射線も、好適に遮
蔽される。
Furthermore, radiation emitted from the fuel rod portion in the radial direction is also suitably shielded.

また火災事故発生時には、密閉容器8′、8″が破壊さ
れ、その体積分だけ収納空間5内の冷却水の占める容積
が増大するため、冷却水が異状に高圧な圧縮水となるこ
とがなく、しかも、収納空間5の頂部及び底部の密閉容
器8′、8″によって収納使用済核燃料7の防衝効果が
得られるという利点がある。
Furthermore, in the event of a fire accident, the airtight containers 8' and 8'' are destroyed, and the volume occupied by the cooling water in the storage space 5 increases by that volume, so that the cooling water does not turn into abnormally high-pressure compressed water. Moreover, there is an advantage that the sealed containers 8', 8'' at the top and bottom of the storage space 5 provide an impact protection effect for the stored spent nuclear fuel 7.

すなわち、使用済核燃料の輸送容器は、規定により帥の
高さから自由に落下衝撃を受けても、その該的安全性を
有することが要求されるが、本考案ではその場合、最も
大きな衝撃力を発生する使用済核燃料容器の軸方向落下
に際したて、収納空間5の頂部及び底部の密閉容器8′
、8″が収納使用済核燃料に対してショックアブソーバ
の機能を発揮することとなるので、その核的安全性が確
保されるという利点がある。
In other words, the spent nuclear fuel transportation container is required to have sufficient safety even if it is subjected to a free fall impact from a height, but in this case, the present invention When the spent nuclear fuel container falls in the axial direction, the airtight container 8' at the top and bottom of the storage space 5
, 8'' function as a shock absorber for the stored spent nuclear fuel, which has the advantage of ensuring its nuclear safety.

【図面の簡単な説明】[Brief explanation of the drawing]

添付図面は本考案の一実施例の概略縦断面図である。 1:使用済核燃料容器(キャスク)外殻、2:蓋、3:
中性子遮蔽水層、4:冷却用フィン、5:収納空間、6
:バスケット、7:核燃料、8′、8″:内部に減圧さ
れた気相空間を有する密閉容器。
The accompanying drawing is a schematic vertical sectional view of an embodiment of the present invention. 1: Spent nuclear fuel container (cask) outer shell, 2: Lid, 3:
Neutron shielding water layer, 4: Cooling fins, 5: Storage space, 6
: Basket, 7: Nuclear fuel, 8', 8'': Closed container having a reduced pressure gas phase space inside.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 放射線遮蔽材に囲まれた収納空間に、使用済核燃料を挿
入密封して輸送する筒状容器内の水充填領域内の頂部及
び底部に、減圧された気相空間を有し、該水充填領域内
の水の異状な温度上昇に伴なって容易に破壊される構成
の密閉容器をそれぞれ配設し、該筒状容器の胴部外周面
に多数のフィンを突設してなることを特徴とする使用済
核燃料の輸送容器。
A cylindrical container in which spent nuclear fuel is inserted into a storage space surrounded by radiation shielding material and transported in a sealed manner has a depressurized gas phase space at the top and bottom of a water-filled region, and the water-filled region Each of the cylindrical containers has a closed container configured to be easily destroyed due to an abnormal temperature rise of the water inside the container, and a large number of fins are provided protruding from the outer peripheral surface of the body of the cylindrical container. Container for transporting spent nuclear fuel.
JP1978130280U 1978-09-25 1978-09-25 Transport container for spent nuclear fuel Expired JPS6028000Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1978130280U JPS6028000Y2 (en) 1978-09-25 1978-09-25 Transport container for spent nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1978130280U JPS6028000Y2 (en) 1978-09-25 1978-09-25 Transport container for spent nuclear fuel

Publications (2)

Publication Number Publication Date
JPS5547625U JPS5547625U (en) 1980-03-28
JPS6028000Y2 true JPS6028000Y2 (en) 1985-08-23

Family

ID=29095746

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1978130280U Expired JPS6028000Y2 (en) 1978-09-25 1978-09-25 Transport container for spent nuclear fuel

Country Status (1)

Country Link
JP (1) JPS6028000Y2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4634518B1 (en) * 2009-08-25 2011-02-23 三菱重工業株式会社 Fuel assembly shock absorber and fuel assembly storage container

Also Published As

Publication number Publication date
JPS5547625U (en) 1980-03-28

Similar Documents

Publication Publication Date Title
US8718221B2 (en) Method of transferring high level radioactive materials, and system for the same
JP5463412B2 (en) Cask equipment for transporting and / or storing high level waste.
US11410784B2 (en) Passive cooling device for casks containing nuclear fuel
JP2002509608A (en) Apparatus suitable for transport and storage of nuclear fuel rods and use of this apparatus
JP7458492B2 (en) Unventilated cask for nuclear waste storage
KR20190117759A (en) Container for storage and transportation of spent fuel
JPS6028000Y2 (en) Transport container for spent nuclear fuel
KR20230002551A (en) Radioactive Nuclear Waste Storage System with Pressure Surge Protection
US3851179A (en) Shipping cask neutron and heat shield
JP2007071787A (en) Cask and method for handling cask
US3732423A (en) Shipping container for radioactive material
JPH01237499A (en) Basket or radioactive material transport vessel
JPS5930474Y2 (en) Container for transporting spent nuclear fuel
JPS6331755B2 (en)
RU2463677C1 (en) Shipping packaging set for spent fuel assemblies of nuclear reactors
KR101895827B1 (en) Method for long-term storage of waste nuclear fuel
JP7330925B2 (en) cask
KR102721045B1 (en) Nuclear fuel storage system with integral simulating
JPS6318957Y2 (en)
JPS598237Y2 (en) Spent nuclear fuel transport container
JPS61198099A (en) Transport vessel for radioactive body
JPS5926318Y2 (en) Spent nuclear fuel transport container
JP2024061964A (en) Radioactive material storage container and method for manufacturing the same
JP2000002796A (en) Storage container for radioactive material
JPS5957198A (en) Nuclear fuel transporting cask