JPS61195398A - Transport vessel for spent nuclear fuel - Google Patents

Transport vessel for spent nuclear fuel

Info

Publication number
JPS61195398A
JPS61195398A JP60035315A JP3531585A JPS61195398A JP S61195398 A JPS61195398 A JP S61195398A JP 60035315 A JP60035315 A JP 60035315A JP 3531585 A JP3531585 A JP 3531585A JP S61195398 A JPS61195398 A JP S61195398A
Authority
JP
Japan
Prior art keywords
nuclear fuel
spent nuclear
container
gamma ray
inner cylinder
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
JP60035315A
Other languages
Japanese (ja)
Inventor
亮介 本間
正佳 小林
吉田 英俊
丸岡 正信
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.)
Japan Steel Works Ltd
Original Assignee
Japan Steel Works Ltd
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 Japan Steel Works Ltd filed Critical Japan Steel Works Ltd
Priority to JP60035315A priority Critical patent/JPS61195398A/en
Publication of JPS61195398A publication Critical patent/JPS61195398A/en
Pending legal-status Critical Current

Links

Landscapes

  • Cleaning In General (AREA)
  • Containers Having Bodies Formed In One Piece (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔産業上の利用分野〕 未発明は原子力発電所から再処理施設への使用済核燃料
輸送用の容器に関する。
DETAILED DESCRIPTION OF THE INVENTION [Industrial Field of Application] The invention relates to a container for the transportation of spent nuclear fuel from a nuclear power plant to a reprocessing facility.

〔従来の技術〕[Conventional technology]

原子力発電所から再処理施設への使用済核燃料の輸送に
は、輸送用容器が使用されるが、この容器は、容器内に
収納された使用済核燃料からのガンマ線及び中性子の外
部への透過を十分に阻止できる遮蔽性能を有するととも
に、容器内に収納された使用済核燃料から発生する熱を
十分に放散させる性能を具備することが要求される。
Transport containers are used to transport spent nuclear fuel from nuclear power plants to reprocessing facilities, but these containers are designed to prevent gamma rays and neutrons from passing through from the spent nuclear fuel stored inside the container. It is required to have a shielding performance that can sufficiently block the nuclear fuel, as well as a performance that can sufficiently dissipate the heat generated from the spent nuclear fuel stored in the container.

従来の使用済核燃料輸送用容器では、容器の胴体を所要
の肉厚の炭素鋼等でのみ製作するか、あるいは胴体内筒
と外筒との間に鉛を介装してガンマ線を遮蔽するととも
に、胴体の外周を所定厚さの合成樹脂等により被覆して
、中性子を遮蔽する構造のものが採用されている。
In conventional containers for transporting spent nuclear fuel, the body of the container is made only of carbon steel with the required wall thickness, or lead is inserted between the inner and outer cylinders to shield gamma rays. The outer periphery of the body is covered with a synthetic resin or the like of a predetermined thickness to shield neutrons.

〔発明が解決しようとする問題点〕[Problem that the invention seeks to solve]

上記従来の使用済核燃料輸送容器の外部線量率は所定の
法規を満足しているものの、今後予想される輸送量の増
大に伴なう輸送従事者の被曝を現在以上に低減させると
か必要になる。
Although the external dose rate of the conventional spent nuclear fuel transport containers mentioned above satisfies the prescribed regulations, it will be necessary to reduce the radiation exposure of transport workers even more than the current level due to the expected increase in the amount of transported nuclear fuel in the future. .

また、Cの種輸送容器は重量制限があるので炭素鋼ある
いは低合金鋼のみで製作する場合、所定のガンマ線遮蔽
性能を得るには、この胴体の肉厚を厚くしなければなら
ず、そのため、内部に収納する使用済核燃料を量を少な
くしなければならないという問題点がある。
In addition, since there is a weight limit on type C transport containers, if they are manufactured only from carbon steel or low-alloy steel, the wall thickness of the body must be increased in order to obtain the desired gamma ray shielding performance. There is a problem in that the amount of spent nuclear fuel stored inside must be reduced.

一方、容器の胴体を外筒と内筒とにより構成し、これら
の中間層に鉛を介装して製作した場合、鉛はその融点が
低いため輸送中に火災事故が発生した場合、鉛が溶融し
、容器の健全性を損ねる可能性がないとは言えない。
On the other hand, if the body of the container is made up of an outer cylinder and an inner cylinder, and lead is interposed in the middle layer between them, lead has a low melting point, so if a fire occurs during transportation, the lead will It cannot be said that there is no possibility that it will melt and damage the integrity of the container.

本発明は、上記従来の問題を解決し、優れたガンマ線遮
蔽性能を有し、使用済核燃料輸送において、従事者の被
曝を低減させるとともに、使用済核燃料の収納量を増大
して輸送効率を向上させ、さらに劣化ウラン金属の有効
利用ができる使用済核燃料輸送容器を提供することを目
的とするものである・ 〔問題点を解決するための手段〕 本発明における問題点解決の手段は使用済核燃料輸送容
器において、該容器の胴体の内筒にステンレス鋼、外筒
に炭素鋼あるいは低合金鋼を使用し、該内筒と外筒との
間にガンマ線遮蔽体として劣化ウラン金属を介装したこ
とにある。
The present invention solves the above-mentioned conventional problems, has excellent gamma ray shielding performance, reduces radiation exposure of workers during spent nuclear fuel transportation, and improves transportation efficiency by increasing the amount of spent nuclear fuel stored. The object of the present invention is to provide a spent nuclear fuel transport container that can effectively utilize depleted uranium metal. In a transportation container, the inner cylinder of the container body is made of stainless steel, the outer cylinder is made of carbon steel or low alloy steel, and depleted uranium metal is interposed between the inner cylinder and the outer cylinder as a gamma ray shield. It is in.

〔作  用〕[For production]

劣化ウラン金属の最も重要な性質は比重が大きいことで
ある。
The most important property of depleted uranium metal is its high specific gravity.

一般に物質は、比重が大きい程ガンマ線遮蔽能力が大き
い性質をもっており、劣化ウラン金属の遮蔽性能は鉛の
約2倍、鋼の約3.5倍程度である。そのため、同一外
部線量率に抑えるための容器の肉厚は劣化ウランをガン
マ線遮蔽体として使用することによって薄くすることが
でき、従って、使用済核燃料の収納容積を増大すること
ができる。また、劣化ウラン金属は鋼と同程度の融点を
有しており、輸送中の火災事故を想定した場合の安全性
確保の観点からも鉛にくらべ有利である。
In general, substances have a property that the higher the specific gravity, the greater the gamma ray shielding ability, and the shielding ability of depleted uranium metal is about twice that of lead and about 3.5 times that of steel. Therefore, the wall thickness of the container for suppressing the same external dose rate can be reduced by using depleted uranium as a gamma ray shield, and therefore the storage volume of spent nuclear fuel can be increased. In addition, depleted uranium metal has a melting point comparable to that of steel, and is advantageous over lead from the standpoint of ensuring safety in the event of a fire accident during transportation.

〔実  施  例〕〔Example〕

本発明を実施例の図面を参照して説明する。第1図は本
発明の一実施例の横断面図であって、使用済核燃料収納
部Sを囲んで円筒状内筒lが形成され、内筒lは一般に
耐食性を有するステンレス鋼で構成されている。内筒1
と間隔を置いてこの内筒lを囲んで円筒状外筒2が形成
され、内筒lと外筒2どの間の空隙部にガンマ線遮蔽体
3が介装されている。外筒2は一般に炭素鋼または低合
金鋼よりなり、構造的強度を与えるに充分な厚さを有し
ている。ガンマ線遮蔽体3はガンマ線の遮蔽作用の優れ
た劣化ウラン金属からなっている。
The present invention will be described with reference to drawings of embodiments. FIG. 1 is a cross-sectional view of an embodiment of the present invention, in which a cylindrical inner cylinder l is formed surrounding a spent nuclear fuel storage part S, and the inner cylinder l is generally made of corrosion-resistant stainless steel. There is. Inner cylinder 1
A cylindrical outer cylinder 2 is formed surrounding the inner cylinder l with a space therebetween, and a gamma ray shielding body 3 is interposed in the gap between the inner cylinder l and the outer cylinder 2. The outer cylinder 2 is generally made of carbon steel or low alloy steel and has sufficient thickness to provide structural strength. The gamma ray shielding body 3 is made of depleted uranium metal which has an excellent gamma ray shielding effect.

第2図は本発明の一実施例の組立縦断面図である。この
図において、円筒状の内筒lの外周に円筒状のガンマ線
遮蔽体3がしまりばめにより装着され、ガンマ線遮蔽体
3の外周に外筒2がしまりばめにより装着され、内筒l
および外筒2の上端にはフランジ4.下端には底板5が
溶接により装着されガンマ線遮蔽体3を密封している。
FIG. 2 is an assembled vertical sectional view of one embodiment of the present invention. In this figure, a cylindrical gamma ray shielding body 3 is attached to the outer circumference of a cylindrical inner tube l by tight fit, an outer tube 2 is attached to the outer circumference of the gamma ray shielding body 3 by tight fit, and an inner tube l
and a flange 4 at the upper end of the outer cylinder 2. A bottom plate 5 is attached to the lower end by welding to seal the gamma ray shield 3.

〔発明の効果〕〔Effect of the invention〕

未発明において、使用済核燃料輸送容器の胴部筒体の内
筒と外筒との間に劣化ウラン金属をガンマ線遮蔽体とし
て介装することによって、劣化ウラン金属の優れたガン
マ線遮蔽性能により、従来の容器と比較して容器全体の
肉厚を薄くすることが可能となり、従って、使用済核燃
料を収容する容積を増大することができて、輸送効率が
向上した。又、従事者の被曝を低減させることも可能と
なった。更に、従来の鉛をガンマ線遮蔽材として使用す
る容器と比較して、輸送中の火災事故において、ガンマ
線遮蔽材が損傷する等の懸念が解消された。
By interposing depleted uranium metal as a gamma ray shielding body between the inner cylinder and the outer cylinder of the body cylinder of a spent nuclear fuel transport container, the excellent gamma ray shielding performance of depleted uranium metal can It has become possible to reduce the wall thickness of the entire container compared to the previous container, and therefore, the capacity for accommodating spent nuclear fuel can be increased, improving transportation efficiency. It has also become possible to reduce the radiation exposure of workers. Furthermore, compared to conventional containers using lead as a gamma ray shielding material, concerns such as damage to the gamma ray shielding material in the event of a fire accident during transportation are eliminated.

そして、劣化ウラン金属は原子力発電に供される核燃料
の製造過程及び使用済核燃料の再処理過程において、大
量に生成されており、本発明によって、劣化ウラン金属
の有効利用が可能となった。
Depleted uranium metal is produced in large quantities in the process of manufacturing nuclear fuel used in nuclear power generation and in the process of reprocessing spent nuclear fuel, and the present invention has made it possible to effectively utilize depleted uranium metal.

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

第1図は本発明の一実施例の横断面図、第2図は本発明
の一実施例の組立縦断面図である。 1−m−内筒、    2−m−外筒、3−−−ガンマ
線遮蔽体、 4−一一フランジ、   5−一一代板。 第1図 第2図
FIG. 1 is a cross-sectional view of one embodiment of the present invention, and FIG. 2 is an assembled vertical cross-sectional view of one embodiment of the present invention. 1-m-inner cylinder, 2-m-outer cylinder, 3--gamma ray shield, 4--11 flange, 5--11 plate. Figure 1 Figure 2

Claims (1)

【特許請求の範囲】[Claims] 使用済核燃料輸送容器において、該容器の胴体の内筒に
ステンレス鋼、外筒に炭素鋼あるいは低合金鋼を使用し
、該内筒と外筒との間にガンマ線遮蔽体として劣化ウラ
ン金属を介装したことを特徴とする使用済核燃料輸送容
器。
In a spent nuclear fuel transportation container, the inner cylinder of the body of the container is made of stainless steel, the outer cylinder is made of carbon steel or low alloy steel, and depleted uranium metal is used as a gamma ray shield between the inner cylinder and the outer cylinder. A spent nuclear fuel transport container characterized by:
JP60035315A 1985-02-26 1985-02-26 Transport vessel for spent nuclear fuel Pending JPS61195398A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60035315A JPS61195398A (en) 1985-02-26 1985-02-26 Transport vessel for spent nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60035315A JPS61195398A (en) 1985-02-26 1985-02-26 Transport vessel for spent nuclear fuel

Publications (1)

Publication Number Publication Date
JPS61195398A true JPS61195398A (en) 1986-08-29

Family

ID=12438371

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60035315A Pending JPS61195398A (en) 1985-02-26 1985-02-26 Transport vessel for spent nuclear fuel

Country Status (1)

Country Link
JP (1) JPS61195398A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2002025670A1 (en) * 2000-09-20 2002-03-28 Hitachi, Ltd. Container for nuclear fuel transportation
JP2002236199A (en) * 2001-02-06 2002-08-23 Ishikawajima Harima Heavy Ind Co Ltd Container and method for storing vitrified body

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2002025670A1 (en) * 2000-09-20 2002-03-28 Hitachi, Ltd. Container for nuclear fuel transportation
JP2002236199A (en) * 2001-02-06 2002-08-23 Ishikawajima Harima Heavy Ind Co Ltd Container and method for storing vitrified body

Similar Documents

Publication Publication Date Title
US5015863A (en) Radiation shield and shielding material with excellent heat-transferring property
EP0757361B1 (en) Transport/storage cask for a radioactive material
US4339411A (en) Shielding container for the transportation and/or for storage of spent fuel elements
US5334847A (en) Composition for radiation shielding
US4569818A (en) Container for storing radioactive material
US5894134A (en) Shipping container for radioactive material
CN110506310A (en) The container of storage and transport spent fuel
US8822964B2 (en) Radioactive substance storage container
JP5808303B2 (en) Radioactive material transport storage container
JP4082179B2 (en) Spent nuclear fuel storage container
JPS61195398A (en) Transport vessel for spent nuclear fuel
JPS63760B2 (en)
GB2165795A (en) Spent fuel storage cask having improved fins
GB1423561A (en) Container for transporting radioactive materials
JPH01124799A (en) Buffer body for radioactive material transporting container
JP3502100B2 (en) Container for nuclear fuel assembly with non-circular forged steel body
JP4815100B2 (en) Transport and storage containers for radioactive materials that generate heat, especially spent nuclear fuel elements or high-level radioactive waste-glass solids
JP2692215B2 (en) Storing method of fuel assembly in spent fuel cask
JPS5930474Y2 (en) Container for transporting spent nuclear fuel
US20240177879A1 (en) Assembly for transporting uranium hexafluoride, comprising shock absorber caps
Ko et al. Design Features of an OASIS-32D Metal Cask for both Transport and Storage of SNF
JP2002257990A (en) Container for containing radioactive substance
JPS62242896A (en) Structure of spent fuel transport-storage vessel
Bader et al. Transportation Cask for Bare High Burnup Used Nuclear Fuel–16362
JPS61160098A (en) Transport vessel for radioactive solid waste