JPS5930474Y2 - Container for transporting spent nuclear fuel - Google Patents
Container for transporting spent nuclear fuelInfo
- Publication number
- JPS5930474Y2 JPS5930474Y2 JP1978124998U JP12499878U JPS5930474Y2 JP S5930474 Y2 JPS5930474 Y2 JP S5930474Y2 JP 1978124998 U JP1978124998 U JP 1978124998U JP 12499878 U JP12499878 U JP 12499878U JP S5930474 Y2 JPS5930474 Y2 JP S5930474Y2
- Authority
- JP
- Japan
- Prior art keywords
- container
- water
- nuclear fuel
- water layer
- temperature
- 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
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【考案の詳細な説明】
本考案は、使用済核燃料を輸送するための容器、特に外
部火災に対する保護処置を施した容器に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a container for transporting spent nuclear fuel, particularly a container provided with external fire protection.
原子力発電所等の原子炉内で一定の反応を終えた核燃料
は、原子炉外に取り出される。Nuclear fuel that has completed a certain reaction inside a nuclear reactor such as a nuclear power plant is taken out of the reactor.
前記核燃料は、通常使用済核燃料と称されるが、原子炉
から取り出された後、所定期間貯蔵ピット内におかれ、
しかる後再処理工場に運ばれる。The nuclear fuel is usually referred to as spent nuclear fuel, and after being removed from the reactor, it is placed in a storage pit for a predetermined period of time.
It is then transported to a reprocessing plant.
しかして、使用済核燃料＆主、運搬しうる状態になって
も、なお、中性子、γ−を発生し続け、かつ崩壊熱を発
生し続けるので、これを輸送するための容器（以下「キ
ャスク」という。However, even when the spent nuclear fuel is in a state where it can be transported, it still continues to generate neutrons, γ-, and decay heat. That's what it means.
）は、次の性能を有することが要求されている。) is required to have the following performance.
（イ） 中性子、γ線を遮蔽できること。(b) Must be able to shield neutrons and gamma rays.
（ロ）崩壊熱を外部に放散し、キャスク内温度即ち核燃
料の温度を一定値以下に保持できること。(b) It is possible to dissipate decay heat to the outside and maintain the temperature inside the cask, that is, the temperature of the nuclear fuel, below a certain value.
（ハ）衝撃荷重、外圧、内圧に耐える強度を有すること
。(c) Must have the strength to withstand impact loads, external pressure, and internal pressure.
に）輸送時に万一外部火災に遭遇した場合にも上記性能
を保持し安全であること。2) The product must maintain the above performance and be safe even in the event of an external fire during transportation.
（ホ）輸送を容易にするため軽量であること。(e) It should be lightweight to facilitate transportation.
上記のような要求性能を満すため、従来第１図に示すよ
うなキャスクが案出されていた。In order to satisfy the above required performance, a cask as shown in FIG. 1 has been devised.
第１図において、０１は、外周面に放熱フィン０２を有
する鋼製容器本体、０３は、本体０１の内側に添設され
た鉛製の遮蔽層、０４は、蓋０５によって密閉された水
０６中に収納された燃料集合体である。In FIG. 1, 01 is a steel container body having radiation fins 02 on the outer peripheral surface, 03 is a lead shielding layer attached to the inside of the main body 01, and 04 is a water 06 sealed with a lid 05. This is a fuel assembly housed inside.
しかるに、前記した従来装置においては、外部火災によ
る熱が、本体０１かも遮蔽層０３に直接伝達され鉛がそ
の融点（３２７℃）以上になって溶融し、放射能の遮蔽
性能が低下したり、反面それを防ごうとして本体０１の
肉厚を増大すると重量が過大になったりして、前記要求
性能を十分満足できないという不具合があった。However, in the conventional device described above, the heat from the external fire is directly transmitted to the main body 01 or the shielding layer 03, and the lead melts at a temperature exceeding its melting point (327° C.), resulting in a decrease in radiation shielding performance. On the other hand, if the thickness of the main body 01 was increased in an attempt to prevent this, the weight would become excessive, resulting in a problem that the above-mentioned required performance could not be fully satisfied.
本考案は、前述の従来のものの不具合に鑑みなされたも
ので、前述の要求性能を総て満す、特に小形、軽量でか
つ外部火災に遭遇しても放射線遮蔽性能が低下しない輸
送用キャスクを提供することを目的とする。The present invention was devised in view of the above-mentioned problems with the conventional products.The present invention was developed to create a transportation cask that satisfies all of the above-mentioned performance requirements, is particularly small, lightweight, and does not deteriorate its radiation shielding performance even if it encounters an external fire. The purpose is to provide.
以下、図示の実施例に基づいて本考案を説明する。Hereinafter, the present invention will be explained based on the illustrated embodiments.
第２図において、樽状の容器１は、外周面に多数の放熱
フィン２が並設されており、容器１の内部には、鉛製の
円筒３がほぼ同軸に挿着されている。In FIG. 2, a barrel-shaped container 1 has a large number of radiation fins 2 arranged in parallel on its outer peripheral surface, and a lead cylinder 3 is inserted almost coaxially into the interior of the container 1.
円筒３と容器１０間の環状の空間には、水が充填されて
水層４を形成している。The annular space between the cylinder 3 and the container 10 is filled with water to form a water layer 4.
容器１の上方開口部には、蓋５が密着接合されている。A lid 5 is tightly joined to the upper opening of the container 1.
燃料集合体６（使用済核燃料は、通常この状態で輸送さ
れる）は、円筒３と蓋５とによって形成された水室７内
に、図示しない支持部材を介して固定されている。The fuel assembly 6 (spent nuclear fuel is normally transported in this state) is fixed in a water chamber 7 formed by the cylinder 3 and the lid 5 via a support member (not shown).
円筒３には、軸方向に離れて少くとも２個の破壊板８が
設けられている。The cylinder 3 is provided with at least two rupture plates 8 spaced apart in the axial direction.
破壊板８は、鉛の融点より低い温度で溶融する合金（活
字合金、はんだ等）で構成されている。The destruction plate 8 is made of an alloy (type alloy, solder, etc.) that melts at a temperature lower than the melting point of lead.
前記した構成を有する本実施例において、燃料集合体６
を収納し、又は取り出すときは、蓋５は、容器１から取
り出され、輸送中は図示のように取付けられている。In this embodiment having the above-described configuration, the fuel assembly 6
When storing or taking out the container 1, the lid 5 is removed from the container 1 and is attached as shown during transportation.
燃料集合体６かも放射される中性子は、水層４及び氷室
７中の水によって遮蔽され、γ線は鉛製の円筒３によっ
て遮蔽される。Neutrons emitted from the fuel assembly 6 are shielded by the water in the water layer 4 and the ice chamber 7, and gamma rays are shielded by the lead cylinder 3.
又燃料集合体６より発生される崩壊熱は、水室１、円筒
３及び水層４を伝わり、容器１の外面およびフィン２０
表面から大気空間に放散し、容器１の内部及び燃料集合
体６は、所定の温度以下に保持される。Further, the decay heat generated by the fuel assembly 6 is transmitted through the water chamber 1, the cylinder 3, and the water layer 4, and is transmitted to the outer surface of the container 1 and the fins 20.
It radiates into the atmosphere from the surface, and the inside of the container 1 and the fuel assembly 6 are maintained at a predetermined temperature or lower.
円筒３に設けられた破壊板８は、水室７と水層４の連通
を遮断しており、水室７の中の混入不純物が水層４へ侵
入することを防止し、更に水層４の温度を水室７より低
く保持している。A destruction plate 8 provided in the cylinder 3 blocks communication between the water chamber 7 and the water layer 4, prevents impurities in the water chamber 7 from entering the water layer 4, and further prevents the water layer 4 from entering the water layer 4. The temperature of the water chamber 7 is maintained lower than that of the water chamber 7.
輸送中、遭遇した外部火災による大量の熱は、フィン２
及び容器１より、水層４に伝えられ、水層４の温度を上
昇させる。During transportation, a large amount of heat from an external fire encountered will cause the fin 2
This is transmitted from the container 1 to the water layer 4, raising the temperature of the water layer 4.
この時、熱伝達の関係から一般に円筒３の温度は、水層
４の温度以下である。At this time, the temperature of the cylinder 3 is generally lower than the temperature of the water layer 4 due to heat transfer.
水層４の温度が、所定の温度に達すると、破壊板８は、
溶融して破壊され、水層４と水室７とが連通し、水の対
流現象が発生し、水室７の水温と水層４の水温はほぼ同
じとなる。When the temperature of the water layer 4 reaches a predetermined temperature, the destruction plate 8
It is melted and destroyed, and the water layer 4 and the water chamber 7 communicate with each other, a water convection phenomenon occurs, and the water temperature in the water chamber 7 and the water temperature in the water layer 4 become almost the same.
円筒３の温度は、前記水の温度上昇に伴って徐々に上昇
する。The temperature of the cylinder 3 gradually increases as the temperature of the water increases.
前記した構成及び作用を有する本実施例によれば、外部
火災による熱は、容器１かも直接円筒３に伝わらず、熱
容量の大きい水層４を介して円筒３に伝わりかつ、円筒
３の溶融点以下で水層４と水密空間Ｔとが連通して対流
が生じ、水の熱容量が大きいため、その温度上昇速度が
従来のものに比して低くなると共に、局部的な温度上昇
が防止されるので、鉛製の円筒３の溶融が防止されて、
放射線の遮蔽性能が低下しないというすぐれた効果を奏
する。According to this embodiment having the above-described configuration and operation, heat from an external fire is not transmitted directly to the cylinder 3 either in the container 1 or in the cylinder 3 through the water layer 4 having a large heat capacity, and is transmitted to the cylinder 3 through the water layer 4 having a large heat capacity. Below, the water layer 4 and the watertight space T communicate with each other to generate convection, and since the heat capacity of the water is large, the rate of temperature rise is lower than that of conventional ones, and local temperature rises are prevented. Therefore, melting of the lead cylinder 3 is prevented,
It has an excellent effect of not reducing radiation shielding performance.
通常時、水室７の水は破壊板８によって妨げられて水層
４へ入らないから、例え水室７の水に放射性物質が核燃
料と共に混入しても、鉛製の円筒３、水層４等によって
遮蔽されるので、外部へ出る放射線が大きくなることは
な（・０
しかも、容器１の肉厚などを増大せずに、軽量かつ熱容
量の大きい、しかも中性子遮蔽性能の大きい水層４を設
けたので、前記要求性能を十分に満たすことができる。Under normal conditions, the water in the water chamber 7 is blocked by the rupture plate 8 and does not enter the water layer 4. Therefore, even if radioactive materials are mixed into the water in the water chamber 7 together with nuclear fuel, the water in the lead cylinder 3 and the water layer 4 etc., so that the amount of radiation emitted to the outside does not increase (・0 Moreover, the water layer 4, which is lightweight, has a large heat capacity, and has a high neutron shielding performance, can be created without increasing the thickness of the container 1. With this provision, the above-mentioned required performance can be fully satisfied.
第１図は、従来装置を示す説明図、第２図は本考案の実
施例を示す説明図である。
１・・・・・・容器、′・２・・・・・・フィン、３・
・・・・・円筒、４・・・・・・水層、５・・・・・・
蓋、７・・・・・・水室、８・・・・・・破壊板。FIG. 1 is an explanatory diagram showing a conventional device, and FIG. 2 is an explanatory diagram showing an embodiment of the present invention. 1... Container, '2... Fin, 3.
...Cylinder, 4...Water layer, 5...
Lid, 7... Water chamber, 8... Destruction plate.
Claims (1)
され同容器の鋼製外殻との間に水層を形成した鉛製遮蔽
筒、同遮蔽筒に設けられた少くとも２個の破壊板、及び
前記容器を封止する蓋を有してなり、鉛より低い融点を
もつ合金で前記破壊板を構成すると共に輸送姿勢におい
て上下方向に間隔を有するように前記破壊板を配置し、
前記遮蔽筒内に注入された水の中に核燃料を収納するこ
とを特徴とする使用済核燃料の輸送用容器。A barrel-shaped container with radiation fins on the outer circumferential surface, a lead shielding tube inserted into the container and forming a water layer between it and the steel outer shell of the container, and at least two pieces installed in the shielding tube. a rupture plate, and a lid for sealing the container, the rupture plate is made of an alloy having a melting point lower than lead, and the rupture plates are arranged so as to be spaced apart from each other in the vertical direction in a transportation posture. ,
A container for transporting spent nuclear fuel, characterized in that nuclear fuel is stored in water injected into the shield cylinder.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1978124998U JPS5930474Y2 (en) | 1978-09-12 | 1978-09-12 | Container for transporting spent nuclear fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1978124998U JPS5930474Y2 (en) | 1978-09-12 | 1978-09-12 | Container for transporting spent nuclear fuel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5542143U JPS5542143U (en) | 1980-03-18 |
| JPS5930474Y2 true JPS5930474Y2 (en) | 1984-08-30 |
Family
ID=29085509
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1978124998U Expired JPS5930474Y2 (en) | 1978-09-12 | 1978-09-12 | Container for transporting spent nuclear fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5930474Y2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2108036B (en) * | 1981-10-26 | 1985-05-22 | British Nuclear Fuels Ltd | Container for irradiated nuclear fuel |
| JP6241869B2 (en) * | 2013-07-31 | 2017-12-06 | 一般財団法人電力中央研究所 | Concrete cask heat removal device and concrete cask |
-
1978
- 1978-09-12 JP JP1978124998U patent/JPS5930474Y2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5542143U (en) | 1980-03-18 |
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