JPS61144597A - Square cylindrical body for absorbing neutron - Google Patents

Square cylindrical body for absorbing neutron

Info

Publication number
JPS61144597A
JPS61144597A JP59267101A JP26710184A JPS61144597A JP S61144597 A JPS61144597 A JP S61144597A JP 59267101 A JP59267101 A JP 59267101A JP 26710184 A JP26710184 A JP 26710184A JP S61144597 A JPS61144597 A JP S61144597A
Authority
JP
Japan
Prior art keywords
stainless steel
rectangular
austenitic stainless
cylinder
neutron absorption
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
JP59267101A
Other languages
Japanese (ja)
Inventor
博司 坂本
岡田 孝継
大石 誠之
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
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group Co 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 Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP59267101A priority Critical patent/JPS61144597A/en
Publication of JPS61144597A publication Critical patent/JPS61144597A/en
Pending 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

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] 本発明は使用済み燃料貯蔵ラックに使用される中性子吸
収能がすぐれた中性子吸収用角筒体に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a neutron absorbing rectangular cylinder with excellent neutron absorbing ability used in a spent fuel storage rack.

[発明の技術的前日とその問題点] 従来の中性子吸収材と強度部材を併用している原子炉用
便用済み燃料貯蔵ラック用角筒体はたて長で第5図に示
したように横断面が正方形の内筒1と外筒2とから形成
されており、内筒1と外筒2との間に中性子吸収材3を
挿入した形状が採られている。
[Technical aspects of the invention and its problems] The rectangular cylindrical body for a spent fuel storage rack for a nuclear reactor, which uses both a conventional neutron absorbing material and a strength member, has a vertical length as shown in Fig. 5. It is formed of an inner cylinder 1 and an outer cylinder 2 with a square cross section, and a neutron absorbing material 3 is inserted between the inner cylinder 1 and the outer cylinder 2.

そして、四隅のコーナ部にはスペーサ4が介在されてい
る。この角筒体における内筒1および外筒2はそれぞれ
寸法公差が厳しくなっており、また加工性が悪い。その
うえ中性子吸収材3は^筒体の強度には寄与していない
。そのため、角筒体の肉厚が大きくなって占積率が大き
くなり、燃料貯蔵ラックとしての高密度化がはかれず、
まIc重量が重くなる欠点を有している。
Spacers 4 are interposed at the four corners. The inner cylinder 1 and outer cylinder 2 in this rectangular cylinder each have strict dimensional tolerances and have poor workability. Moreover, the neutron absorbing material 3 does not contribute to the strength of the cylinder. As a result, the wall thickness of the rectangular cylinder increases and the space factor increases, making it difficult to achieve high density as a fuel storage rack.
However, it has the disadvantage that the Ic weight is heavy.

原子カプラントにおいて、原子炉炉心から取出された使
用済み燃料は再処理するまでの間一旦保管される。近年
使用済み燃料プール(以下プールと称す)内のスペース
を有効に利用するため、貯蔵燃料の間隔をせまくする改
良がなされており、この思想に基づいたラックを高密度
ラックと称している。貯蔵ラックは燃料が相互間の影響
により臨界に達しない構造に形成する必要があるが、貯
蔵する燃料同志の間隔をせまくするため前述したように
内筒1と外筒2との間に中性子吸収材3を挿入している
In a nuclear couplant, spent fuel removed from a nuclear reactor core is temporarily stored until it is reprocessed. In recent years, in order to effectively utilize the space within a spent fuel pool (hereinafter referred to as a pool), improvements have been made to narrow the spacing between stored fuels, and racks based on this idea are referred to as high-density racks. It is necessary to form the storage rack in such a structure that the fuel does not reach criticality due to mutual influence, but in order to narrow the distance between the fuels to be stored, as mentioned above, there is a neutron absorbing structure between the inner cylinder 1 and the outer cylinder 2. Material 3 is being inserted.

また、貯蔵ラックは燃料を貯蔵するためのものなので、
耐震性の面からも重要な機器であり、十分な強度を有し
ていな番プればならない。しかしながら、従来の貯蔵ラ
ックは第5図から明らかなように内筒1と外筒2との間
に中性子吸収材3を挿入しているため、角筒体の肉厚が
大になり、高密度ラックとしての高密度化は期待できな
い。
Also, storage racks are for storing fuel, so
It is also an important piece of equipment from the standpoint of earthquake resistance, and must have sufficient strength. However, as is clear from Fig. 5, in the conventional storage rack, the neutron absorbing material 3 is inserted between the inner cylinder 1 and the outer cylinder 2, so the wall thickness of the rectangular cylinder becomes large and the density is high. High density racks cannot be expected.

なお、中性子吸収断面積が大きい元素を添加した合金そ
のもので角筒体を構成することも考えられるが、一般に
この種の合金は、脆く、伸びが小さいため、角筒体への
加工性が極めて難かしいなどの欠点がある。
It is also possible to construct the rectangular tube using an alloy itself containing an element with a large neutron absorption cross section, but this type of alloy is generally brittle and has low elongation, making it extremely difficult to form it into a rectangular tube. It has drawbacks such as being difficult.

[発明の目的1 本発明の目的は上記欠点を解決するためになされたもの
で、加工性および溶接性がすぐれ、かつすき21′腐食
を生じることがなく強度が十分骨られるとともに薄肉化
が容易で高密度化し得る使用済み燃料貯蔵ラックに適し
た中性子吸収用角筒体を提供することにある。
[Objective of the Invention 1 The object of the present invention has been made to solve the above-mentioned drawbacks, and has excellent workability and weldability, does not cause crevice corrosion, has sufficient strength, and can be easily thinned. An object of the present invention is to provide a neutron absorbing rectangular cylinder suitable for a spent fuel storage rack that can be made to have a high density.

[発明の概要] 本発明の中性子吸収角筒体は、中性子吸収断面積が大き
い元素を添加した合金をオーステナイト系ステンレス鋼
に圧延クラッドし、オーステナイト系ステンレス鋼が外
側になるように形成されていることを特徴とする。
[Summary of the Invention] The neutron absorbing rectangular cylinder of the present invention is formed by rolling cladding of austenitic stainless steel with an alloy added with an element having a large neutron absorption cross section so that the austenitic stainless steel is on the outside. It is characterized by

中性子吸収材となる合金は、曲げ加工時に圧縮を受ける
側となり割れが発生しにくい。また中性子吸収材となる
合金とオーステナイト系ステンレス鋼は圧延により金属
結合するためすきまを生じることがないので、この部分
の選択腐食の懸念がない。
The alloy that serves as the neutron absorber is subject to compression during bending, making it less likely to crack. Furthermore, since the alloy serving as the neutron absorbing material and the austenitic stainless steel are metallically bonded by rolling, no gaps are created, so there is no concern about selective corrosion in this part.

さらに中性子吸収材が強度に寄与する合金となりている
ため、角筒体の肉厚を厚くする必要がなく、その結果と
して大幅なラックの高密度化が可能となる。
Furthermore, since the neutron absorbing material is an alloy that contributes to strength, there is no need to increase the wall thickness of the rectangular cylinder, and as a result, it is possible to significantly increase the density of the rack.

中性子吸収断面積の大きい元素としては、ハフニウム、
ユーロピウム等があるが、安価に入手できるボロンが望
ましい。また、これらの元素を添加する合金としてはN
i基合金、オーステナイト系ステンレス鋼等があるが、
圧延クラツド鋼板の施工性、耐食性および価格の点等か
らオーステナイト系ステンレス…を選ぶことが望ましい
Elements with large neutron absorption cross sections include hafnium,
There are europium, etc., but boron is preferable because it is available at low cost. In addition, as an alloy to which these elements are added, N
There are i-base alloys, austenitic stainless steels, etc.
It is desirable to choose austenitic stainless steel from the viewpoints of workability, corrosion resistance, and price of the rolled clad steel plate.

ざらにオーステナイト系ステンレス鋼に添加するボロン
の量は1%以上に選ぶことにより、未臨界性を維持する
のに必要な薄肉化した厚さを得ることができる。
By selecting the amount of boron added to the austenitic stainless steel to be 1% or more, it is possible to obtain the thinner thickness necessary to maintain subcriticality.

[発明の実施例] 以下第1図から第4図を参照しながら本発明に係る中性
子吸収用角筒体の一実施例を説明する。
[Embodiment of the Invention] An embodiment of the neutron absorbing rectangular cylinder according to the present invention will be described below with reference to FIGS. 1 to 4.

第1図は本発明に係る角筒体の横断面を示したもので、
たて艮の外05はオーステナイト系ステンレス鋼(以下
304と記す)であり、たて長の内筒6はボロン添加オ
ーステナイト系ステンレス鋼(以下304Bと記す)で
形成されている。この両者は圧延クラッドにした鋼板に
よって角筒状に形成されている。
FIG. 1 shows a cross section of a rectangular cylinder according to the present invention.
The outer tube 05 of the vertical tube is made of austenitic stainless steel (hereinafter referred to as 304), and the vertical inner tube 6 is made of boron-added austenitic stainless steel (hereinafter referred to as 304B). Both of these are formed into a rectangular tube shape using rolled clad steel plates.

304Bは、重量%で8〜14%のNi、16〜20%
のCr残部Feと不純物からなる304にボロン(8)
を重量で2%添加したものである。クラツド鋼板はこれ
らの304板と304B板を表面を清浄に処理した後、
積層し、各端部を溶接により封止し、900〜i、os
o℃の温度範囲で所望の厚さに圧延したものである。
304B is 8-14% Ni, 16-20% by weight
Boron (8) in 304 consisting of Cr remainder Fe and impurities
2% by weight was added. Clad steel plates are made by cleaning the surfaces of these 304 plates and 304B plates, and then
Laminated, each end sealed by welding, 900~i, os
It is rolled to a desired thickness at a temperature range of 0°C.

角筒体はこの圧延クラツド鋼板を部分的に一隅だけ示し
た第2図のように所望の寸法に曲げ加工によって形成す
る。曲げ加工の際、304B部の延性が不足する場合は
曲げ加工前に第3図に示したように304Bの内筒6材
に溝7をあらかじめ加工しておく。この溝7により容易
に曲げ加工が可能となる。
The rectangular cylinder is formed by bending this rolled clad steel plate into desired dimensions as shown in FIG. 2, which shows only one corner. If the ductility of the 304B portion is insufficient during bending, a groove 7 is previously formed in the inner cylinder 6 material of 304B as shown in FIG. 3 before bending. This groove 7 allows easy bending.

このように形成した角筒体を積み重ねてラックを構成し
た場合には、燃料が臨界に達するのを防ぐよう十分な中
性子吸収能を保持しなければならない。A−ステナイト
系ステンレス鋼にボロンを多量に含有すると延性が低下
し、加工性の面からは好ましくないが、前記未臨界性の
ためには一定最以上のボロンを含有するか、または板厚
を大きくしなければならない。
When a rack is constructed by stacking rectangular cylinders formed in this manner, sufficient neutron absorption capacity must be maintained to prevent the fuel from reaching criticality. A- Containing a large amount of boron in stenitic stainless steel reduces ductility and is not preferable from the viewpoint of workability. It has to be bigger.

しかし、板厚をあまり大きくすることは前述したように
ラックの高密度化に逆行する。そこで本発明では高ボロ
ン含有用の304Bに、加工性の良好な通常のボロンを
含有しない304をクラッドして、この問題点を解決し
ている。
However, increasing the plate thickness too much goes against the trend of increasing rack density as described above. Therefore, in the present invention, this problem is solved by cladding the high boron-containing 304B with ordinary boron-free 304 which has good workability.

ボロン添加ステンレス鋼の中性子吸収能は第4図に示し
たような特性を示している。
The neutron absorption capacity of boron-added stainless steel exhibits the characteristics shown in FIG.

なお、図中aはボロンの含有用が0%であり、bは 0
.5重量%、 Cは 1.0@量%、dは 1.5重量
%、eは2.0重量%をそれぞれ示している。
In addition, in the figure, a indicates 0% boron content, and b indicates 0%.
.. 5% by weight, C is 1.0% by weight, d is 1.5% by weight, and e is 2.0% by weight.

この図から明らかなようにボロンの含有用を高くすれば
板厚が薄くてもよいことが認められる。
As is clear from this figure, it is recognized that the plate thickness can be made thinner by increasing the boron content.

ボロンの含有用が1%未満では未臨界性保持のための板
厚が厚く高密度化の効果は小さい。しだがってクラッド
祠である304Bのボロン量は1%以上である事が望ま
しい。
If the boron content is less than 1%, the plate thickness for maintaining subcriticality is too thick, and the effect of increasing density is small. Therefore, it is desirable that the boron content of 304B, which is a cladding, is 1% or more.

なお、この実施例ではボロン含有用を2%としており、
304Bの板厚は2.8龍となっている。
In addition, in this example, the boron content is 2%,
The plate thickness of 304B is 2.8 mm.

角筒体から使用済み燃料ラックを構成する場合はこの角
筒体を積み重ね底板や補強梁を取りつけねばならないが
、溶接性の良好な304をクラッドした場合にはこの部
分を溶接して燃料ラックを組み立てることが可能である
When constructing a spent fuel rack from rectangular cylinders, it is necessary to stack the rectangular cylinders and attach a bottom plate and reinforcing beams, but if the cladding is made of 304, which has good weldability, these parts can be welded to form the fuel rack. It is possible to assemble.

なお、第5図に示した従来の3重構造では外筒2、中性
子吸収材3および内筒1は結合しておらず、十分な強度
を確保するためには内筒1および外筒2をある程度厚く
する必要があった。これに対して、本発明では中性子吸
収材つまり304Bと母材304が完全な金属結合をな
し一体となっているため、全体の厚さを薄くできる。
Note that in the conventional triple structure shown in Fig. 5, the outer cylinder 2, neutron absorber 3, and inner cylinder 1 are not connected, and in order to ensure sufficient strength, the inner cylinder 1 and the outer cylinder 2 must be connected. It needed to be somewhat thicker. In contrast, in the present invention, the neutron absorbing material, that is, 304B, and the base material 304 are integrally bonded with each other through complete metal bonding, so that the overall thickness can be reduced.

[発明の効果コ 以上述べたように、本発明によれば、原子炉用燃料貯蔵
ラックを構成する角筒体を中性子吸収断面積の大きい元
素を添加した304Bを304に圧延クラッドした鋼板
から形成することによって、角筒体の加工性および溶接
性が良好となり、また溝肉化小型化が可能となり、高密
度の燃料貯蔵ラックに好適した中性子吸収用角筒体を提
供することができる。
[Effects of the Invention] As described above, according to the present invention, the rectangular cylinder constituting the fuel storage rack for a nuclear reactor is formed from a steel plate rolled and clad with 304B added with an element having a large neutron absorption cross section. By doing so, the workability and weldability of the rectangular cylinder are improved, and the groove can be made smaller and smaller, and a rectangular cylinder for neutron absorption suitable for a high-density fuel storage rack can be provided.

なお、本発明は上記実施例に限ることなく、たとえば3
048合金を304でサンドインチ状に積層し圧延クラ
ッドした鋼板から角筒を形成することによっても前記実
施例と同等の効果が得られる。
Note that the present invention is not limited to the above embodiments, but includes, for example, 3
Effects similar to those of the above embodiment can also be obtained by forming a rectangular tube from steel plates laminated with 048 alloy in the form of a sandwich inch and rolled and clad.

また、本発明で使用するオーステナイト系ステンレス鋼
は実施例で説明した304のみに限るものではない。
Further, the austenitic stainless steel used in the present invention is not limited to 304 described in the embodiment.

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

第1図は本発明に係る中性子吸収用角筒体の一実施例を
示す横断面図、第2図は第1図の角筒体の角部を折り曲
げた状態を拡大して示す部分断面図、第3図は第2図の
クラット板の折り曲げる前の状態を示す部分断面図、第
4図はオーステナイト系ステンレス鋼へのボロン添加量
と板厚と中性子吸収能の関係を示す特性図、第5図は従
来の中性子吸収用角筒体を示づ横断面図である。 1・・・・・・・・・内 筒 2・・・・・・・・・外 筒 3・・・・・・・・・中性子吸収材 4・・・・・・・・・スペーサ 5・・・・・・・・・オーステナイト系ステンレス鋼外
筒6・・・・・・・・・ボロン添加オーステナイト系ス
テンレス鋼内筒 7・・・・・・・・・満
FIG. 1 is a cross-sectional view showing an embodiment of the rectangular tube for neutron absorption according to the present invention, and FIG. 2 is a partial cross-sectional view showing an enlarged view of the rectangular tube shown in FIG. 1 with its corners bent. , Fig. 3 is a partial cross-sectional view showing the state of the crat plate in Fig. 2 before bending, Fig. 4 is a characteristic diagram showing the relationship between the amount of boron added to austenitic stainless steel, plate thickness, and neutron absorption capacity. FIG. 5 is a cross-sectional view showing a conventional neutron absorbing rectangular cylinder. 1...Inner tube 2...Outer tube 3...Neutron absorbing material 4...Spacer 5 ......Austenitic stainless steel outer cylinder 6...Boron-added austenitic stainless steel inner cylinder 7...Full

Claims (3)

【特許請求の範囲】[Claims] (1)中性子吸収断面積が大きい元素を添加した合金板
の片面にオーステナイト系ステンレス鋼を積層して圧延
クラッドとし、この圧延クラッドから前記中性子吸収断
面積が大きい元素を添加した合金板が内側になるように
角筒状に形成されていることを特徴とする中性子吸収用
角筒体。
(1) Austenitic stainless steel is laminated on one side of an alloy plate containing an element with a large neutron absorption cross section to form a rolled cladding, and from this rolled cladding, an alloy plate containing an element with a large neutron absorption cross section is placed on the inside. A rectangular cylinder for neutron absorption, characterized in that it is formed into a rectangular cylinder shape.
(2)中性子吸収断面積が大きい元素を添加した合金は
ボロンを添加したオーステナイト系ステンレス鋼である
ことを特徴とする特許請求の範囲第1項記載の中性子吸
収用角筒体。
(2) The rectangular cylinder for neutron absorption according to claim 1, wherein the alloy to which an element having a large neutron absorption cross section is added is an austenitic stainless steel to which boron is added.
(3)ボロンを含有するオーステナイト系ステンレス鋼
のボロン含有用は重量で0.1%以上であることを特徴
とする特許請求の範囲第1項記載の中性子吸収用角筒体
(3) The rectangular cylinder for neutron absorption according to claim 1, wherein the boron content of the austenitic stainless steel is 0.1% or more by weight.
JP59267101A 1984-12-18 1984-12-18 Square cylindrical body for absorbing neutron Pending JPS61144597A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59267101A JPS61144597A (en) 1984-12-18 1984-12-18 Square cylindrical body for absorbing neutron

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59267101A JPS61144597A (en) 1984-12-18 1984-12-18 Square cylindrical body for absorbing neutron

Publications (1)

Publication Number Publication Date
JPS61144597A true JPS61144597A (en) 1986-07-02

Family

ID=17440067

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59267101A Pending JPS61144597A (en) 1984-12-18 1984-12-18 Square cylindrical body for absorbing neutron

Country Status (1)

Country Link
JP (1) JPS61144597A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014089166A (en) * 2012-10-31 2014-05-15 Nippon Light Metal Co Ltd Neutron absorber and manufacturing method of the same

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014089166A (en) * 2012-10-31 2014-05-15 Nippon Light Metal Co Ltd Neutron absorber and manufacturing method of the same

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