JPS61153595A - Spent fuel storage rack - Google Patents
Spent fuel storage rackInfo
- Publication number
- JPS61153595A JPS61153595A JP59273631A JP27363184A JPS61153595A JP S61153595 A JPS61153595 A JP S61153595A JP 59273631 A JP59273631 A JP 59273631A JP 27363184 A JP27363184 A JP 27363184A JP S61153595 A JPS61153595 A JP S61153595A
- Authority
- JP
- Japan
- Prior art keywords
- boron
- spent fuel
- storage rack
- fuel storage
- composite material
- 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
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
- Sampling And Sample Adjustment (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】
〔発明の技術分野〕
本発明は使用済みの燃料棒を貯蔵する貯蔵プールで用い
る使用済燃料用貯蔵ラックｌこ関する。TECHNICAL FIELD OF THE INVENTION The present invention relates to spent fuel storage racks for use in storage pools for storing spent fuel rods.
原子炉の使用済燃料は燃料集合体のまま水を入れたプー
ルの中に貯蔵される。核燃料棒は使用済みでありも熱中
性子を放出しているので、燃料集合体は通常厚さ６ｍｍ
のステンレス鋼より成る仕切板で連節されて形成された
セル内に収容され、燃料集合体同志が接触しないように
なっており、また集合体と集合体との間を充分に離して
、放出された熱中性子が隣りの果合体Ｉことどかない様
に配置されている。Spent fuel from a nuclear reactor is stored as a fuel assembly in a pool filled with water. Since nuclear fuel rods still emit thermal neutrons even after they have been used, fuel assemblies are usually 6 mm thick.
The fuel assemblies are housed in cells connected by partition plates made of stainless steel so that they do not come into contact with each other, and the fuel assemblies are kept sufficiently apart from each other to prevent discharge. The thermal neutrons are arranged so that they do not reach the neighboring coalescence I.
ところが近年原子力発電の需要が尚まるにつれて使用済
燃料の量も増力口し、貯蔵プールに保管する使用済燃料
棒の個々の占有面積を大巾に縮少する必要がでてきた。However, as the demand for nuclear power generation has subsided in recent years, the amount of spent fuel has increased, and it has become necessary to significantly reduce the area occupied by each spent fuel rod stored in a storage pool.
そこで燃料集合体のプール内での占有面積を小さくし密
度高く貯蔵するために現在使用している仕切板等セルを
形成する部材を中性子吸収能力のより大きいものに代え
る必要が考えられている。一方貯蔵プールの水温は６０
〜７０℃にも達するためセルを形成する部材は中性子吸
収体でありながら、耐食性が高くかつ半永久的Ｉζ使う
ことのできるものが必要とされる。そこで、オーステナ
イトステンレス鋼中に中性子吸収体であるボロンを添加
したボロン／ステンレス鋼が試みられたことがあるが、
このボロン／ステンレス鋼は圧延、溶接等が難かしくま
たボロンは高々１．５〜２重１１種度しか入れる。こと
ができないため、ボロン／ステンレス鋼としては中性子
吸収能力が少なくセルを形成する部材としては充分なも
のではなかりた。Therefore, in order to reduce the area occupied by fuel assemblies in the pool and store them at a high density, it is considered necessary to replace the currently used members that form the cells, such as partition plates, with ones that have a higher neutron absorption capacity. On the other hand, the water temperature in the storage pool is 60
Since the temperature reaches ~70°C, the members forming the cells are required to be neutron absorbers, but also have high corrosion resistance and can be used semi-permanently. Therefore, attempts have been made to create boron/stainless steel in which boron, which is a neutron absorber, is added to austenitic stainless steel.
This boron/stainless steel is difficult to roll, weld, etc., and boron can only be added at a degree of 1.5 to 2 and 11 degrees. Therefore, boron/stainless steel has a low neutron absorption capacity and is not sufficient as a member for forming cells.
本発明は上記のような問題点に対してなされたもので、
充分な中性子吸収能を有しかつ６０〜７０℃の高温水中
に長期間置かれても充分にたえる耐食性を有した部材に
より形成されたセルよりなる使用済燃料用貯蔵ラックを
提供することを目的とする。The present invention has been made to address the above-mentioned problems.
It is an object of the present invention to provide a spent fuel storage rack consisting of cells formed from members having sufficient neutron absorption capacity and sufficient corrosion resistance even when placed in high-temperature water of 60 to 70°C for a long period of time. purpose.
本発明は原子炉の使用済燃料棒を貯蔵プールに於て、燃
料棒集合ｆ＊を収容するセルを形成する部材として中性
子吸収能を有しかつ耐食性を有したボロンファイバーを
含有した複合材料を用いた使用済燃料用貯蔵ラックであ
ることを特徴としている。第１図にその本発明に係る使
用済燃料用貯蔵ラックの一実施例の斜視図を示す。使用
済燃料の集合体は約１４０ｍｍＸ１４０ｍｍＸ４０００
ｍｍの大きさであり第１図の縦長セルに縦方向に挿入さ
れる。The present invention uses a composite material containing boron fibers that has neutron absorption ability and corrosion resistance as a member for forming cells that accommodate fuel rod assemblies f* in a storage pool for spent fuel rods of a nuclear reactor. It is characterized by being a storage rack for used fuel. FIG. 1 shows a perspective view of an embodiment of a spent fuel storage rack according to the present invention. The spent fuel assembly is approximately 140mm x 140mm x 4000
It has a size of mm and is inserted vertically into the vertically elongated cell in FIG.
このセルを形成する部材として中性子吸収能力の高いボ
ロンを主成分とするボロンファイバーを金属材中に配列
して強化した例えばボロン強化アルミ合金があげられる
。あるいは架橋ポリエチレン等を主成分とする樹脂にボ
ロンファイバーを配列して強化したボロン強化樹脂があ
げられる。使用適燃料から放出される中性子は該ボロン
強化複合材料による仕切板等に吸収され、除々に放射能
を減少していく。これらのボロン強化複合材料のボロン
繊維の分布密度は中性子吸収能と対応゛シ密度が高けれ
ば吸収能が藁くその場合燃料果合体と隣の集合体との距
離と小さくすることが出来、したがりてプール内への収
納数を増加できる。このような該複合材料の素地に用い
る金属としてはこの他にもアルミニウム及びその合金、
チタン及びその合金ステンレス鋼等があげられる。また
他の樹脂としてはテフロン系樹脂、ポリエステル樹脂、
エポキシ系樹脂等温水中での耐食性０強度を備えた樹脂
を用いることができる。As a material for forming this cell, for example, a boron-reinforced aluminum alloy, which is made by arranging boron fibers mainly composed of boron, which has a high neutron absorption ability, in a metal material to strengthen the material, can be cited. Another example is a boron-reinforced resin made by arranging boron fibers in a resin whose main component is crosslinked polyethylene or the like. Neutrons emitted from suitable fuels are absorbed by the partition plates made of the boron-reinforced composite material, and their radioactivity gradually decreases. The distribution density of boron fibers in these boron-reinforced composite materials corresponds to the neutron absorption capacity.The higher the density, the greater the absorption capacity. Therefore, the number of items stored in the pool can be increased. Other metals used for the base material of such composite materials include aluminum and its alloys,
Examples include titanium and its alloys, stainless steel, etc. Other resins include Teflon resin, polyester resin,
Epoxy resin A resin having zero strength and corrosion resistance in isothermal water can be used.
−〔発明の効果〕
本発明のボロン強化複合材料で形成されたセルの中に、
使用済燃料集合体を貯蔵すると、燃料から放出される中
性子をボロンが良く吸収し、又、用いた複合材料の７０
’Ｃ根度の温水中での耐食性が良い為半永久的に貯蔵ラ
ックとして使用できる。- [Effects of the invention] In the cells formed of the boron-reinforced composite material of the present invention,
When spent fuel assemblies are stored, boron absorbs neutrons emitted from the fuel well, and the composite material used
'C Nedo has good corrosion resistance in hot water, so it can be used semi-permanently as a storage rack.
実施例１
約１００μｍφのボロン繊維を強化アルミニウム合金（
６０６１）上に配列し、不活性アルゴン雰囲気でガス炎
溶射してシート状の中間複合素材を得た後、これを積重
ねポットプレス曇こより約３ｍｍ厚のボロン強化複合材
料を得た。Example 1 Boron fibers with a diameter of approximately 100 μm were reinforced with an aluminum alloy (
6061) and sprayed with a gas flame in an inert argon atmosphere to obtain a sheet-like intermediate composite material, which was then stacked and pot-pressed to obtain a boron-reinforced composite material with a thickness of about 3 mm.
第１図Ｅここのボロン強化複合材、料を用いて作製した
使用済燃料貯蔵ラックの一実施例を示す。FIG. 1E shows one embodiment of a spent fuel storage rack fabricated using the boron-reinforced composite material.
断面積が約１４０ｍｍＸ１４０ｍｍ の正四角で高さが
約４０００ｍｍの枠構３をステンレス鋼で作り、その壁
面２に上記複合材料を嵌め込み、燃料集合体を収納する
セル１よりなる貯蔵ラックを形成した。このようにして
作製した貯蔵用ラックはその中性子吸収性及び耐食性共
に実際の使用に対して充分な特性を有していることが確
認された。A frame structure 3 having a square cross-sectional area of about 140 mm x 140 mm and a height of about 4000 mm was made of stainless steel, and the above composite material was fitted into the wall surface 2 of the frame structure 3 to form a storage rack consisting of cells 1 for storing fuel assemblies. It was confirmed that the storage rack thus produced had sufficient properties for practical use in terms of both neutron absorption and corrosion resistance.
実施例２
約１００μｍφのボロン繊維を架橋ポリエチレン樹脂上
に配列し、その上に同架橋ポリエチレン樹脂を流しかた
めることにより約３ｍｍ厚のボロン強化複合材料を得た
。Example 2 Boron fibers with a diameter of about 100 μm were arranged on a cross-linked polyethylene resin, and the cross-linked polyethylene resin was poured onto the resin to obtain a boron-reinforced composite material with a thickness of about 3 mm.
これを用いて実施例１と同様にして燃料果合体を収納す
るセルを有した貯蔵ラックを作製した。Using this, a storage rack having cells for accommodating the fuel assembly was manufactured in the same manner as in Example 1.
このようにして作製した貯蔵用ラックもやはり実施例１
と同様充分な特性を有しているこるが確認された。The storage rack produced in this way is also Example 1.
It was confirmed that this material has sufficient properties similar to those of the above.
第１図は本発明の使用済燃料用貯蔵ラックの一実施例を
模式的に示した斜視図である。
１・・・使用済燃料集合体を収納するセル、２・・・ボ
ロン強化複合材料、３・−枠構。FIG. 1 is a perspective view schematically showing an embodiment of the spent fuel storage rack of the present invention. 1... A cell for storing a spent fuel assembly, 2... A boron-reinforced composite material, 3... A frame structure.
Claims (1)
ーを含有した複合材料により形成されていることを特徴
とする使用済燃料用貯蔵ラック。(1) A spent fuel storage rack characterized in that cells for storing used fuel rods are formed of a composite material containing boron fibers.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59273631A JPS61153595A (en) | 1984-12-27 | 1984-12-27 | Spent fuel storage rack |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59273631A JPS61153595A (en) | 1984-12-27 | 1984-12-27 | Spent fuel storage rack |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS61153595A true JPS61153595A (en) | 1986-07-12 |
Family
ID=17530392
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59273631A Pending JPS61153595A (en) | 1984-12-27 | 1984-12-27 | Spent fuel storage rack |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61153595A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5032348A (en) * | 1988-02-19 | 1991-07-16 | Transnucleaire | Stowage rack for nuclear fuel elements |
-
1984
- 1984-12-27 JP JP59273631A patent/JPS61153595A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5032348A (en) * | 1988-02-19 | 1991-07-16 | Transnucleaire | Stowage rack for nuclear fuel elements |
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