JPH05256995A - Thermal-neutron shielding material - Google Patents
Thermal-neutron shielding materialInfo
- Publication number
- JPH05256995A JPH05256995A JP8751592A JP8751592A JPH05256995A JP H05256995 A JPH05256995 A JP H05256995A JP 8751592 A JP8751592 A JP 8751592A JP 8751592 A JP8751592 A JP 8751592A JP H05256995 A JPH05256995 A JP H05256995A
- Authority
- JP
- Japan
- Prior art keywords
- stainless steel
- boron compound
- powder
- resin
- resistivity
- 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.)
- Withdrawn
Links
Landscapes
- Laminated Bodies (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は，核燃料集合体輸送容
器，核燃料保管容器，使用済み核燃料保管容器などを構
成するのに好適な熱中性子遮蔽材料に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a thermal neutron shielding material suitable for constituting a nuclear fuel assembly transportation container, a nuclear fuel storage container, a spent nuclear fuel storage container and the like.
【０００２】[0002]
【従来の技術】原子力発電所の稼動につれて熱中性子遮
蔽材料の需要が増加している。核燃料集合体輸送容器や
使用済み核燃料の輸送容器，保管容器等を構成する材料
は熱中性子の吸収能を有することが必要である。従来よ
り，これらの材料として，中性子吸収断面積の大きいＢ
（硼素）を含有させたＢ添加オーステナイトステンレス
鋼が知られている。これらの容器はその肉厚をできるだ
け薄くして核燃料の収容量を多くすることが望ましい
が，このためには，該ステンレス鋼中のＢ含有量を多く
することが必要となる。Demand for thermal neutron shielding materials is increasing with the operation of nuclear power plants. It is necessary that the materials constituting the nuclear fuel assembly transportation container, the spent nuclear fuel transportation container, the storage container, etc. have the ability to absorb thermal neutrons. Conventionally, B has a large neutron absorption cross section as these materials.
A B-added austenitic stainless steel containing (boron) is known. It is desirable that the thickness of these containers is made as thin as possible to increase the amount of nuclear fuel that can be accommodated, but for this purpose, it is necessary to increase the B content in the stainless steel.
【０００３】Ｂ含有量を多くしたステンレス鋼は熱間圧
延性，冷間圧延性及び成形性が低下する。特に熱間圧延
性についての悪影響が顕著となる。これは，Ｂ含有量が
多くなるとＢが鋼中に固溶せず，脆いほう化物として析
出するからである。このために熱間圧延時に割れが発生
しやすくなり板の製造が極めて困難となるという問題が
あった。Stainless steel containing a large amount of B deteriorates in hot rolling property, cold rolling property and formability. Especially, the adverse effect on the hot rolling property becomes remarkable. This is because when the B content increases, B does not form a solid solution in steel and precipitates as a brittle boride. For this reason, there is a problem that cracks are likely to occur during hot rolling, making it extremely difficult to manufacture a plate.
【０００４】このようなことから，高Ｂ添加ステンレス
鋼の熱間圧延性の改善について，特公平3-54007号公報,
特開昭63-50429号公報, 特開昭63-96221号公報等で
は，加熱条件, 分塊あるいは熱間圧延条件を厳しく制限
することを提案している。From the above, Japanese Patent Publication No. 3-54007 discloses a method for improving the hot rolling property of high B-added stainless steel.
JP-A-63-50429, JP-A-63-96221, etc. propose to severely limit heating conditions, agglomeration or hot rolling conditions.
【０００５】[0005]
【発明が解決しようとする課題】熱中性子遮蔽材料とし
ての高Ｂ添加ステンレス鋼は，前記のように製造性が悪
いという問題があり，前記公報に提案されている方法の
場合にも，通常のステンレス鋼の場合とは異なる条件で
鋼板を製造しなければならず，また歩留りの向上にも限
界があるから，製造コストが高くなるという問題があ
る。The high B-added stainless steel as a thermal neutron shielding material has the problem of poor manufacturability as described above, and even in the case of the method proposed in the above publication, the usual Since steel plates must be manufactured under conditions different from those for stainless steel, and there is a limit to the improvement in yield, there is the problem of increased manufacturing costs.
【０００６】[0006]
【課題を解決するための手段】本発明によれば，硼素化
合物の粒子を樹脂内に分散含有させてなる樹脂層と，ス
テンレス鋼からなる金属層とを積層してなる熱中性子遮
蔽材料を提供する。According to the present invention, there is provided a thermal neutron shielding material comprising a resin layer containing particles of a boron compound dispersed in a resin and a metal layer made of stainless steel. To do.
【０００７】[0007]
【作用】硼素化合物は熱中性子吸収能を有するので，こ
の硼素化合物の粒子を樹脂内に分散含有させてなる樹脂
層が熱中性子遮蔽層として作用する。ステンレス鋼は形
状と強度を付与する補強材料として作用し，耐食性，耐
衝撃性をもつ核燃料容器を構成することができる。Since the boron compound has the ability to absorb thermal neutrons, the resin layer in which particles of the boron compound are dispersed and contained in the resin acts as a thermal neutron shielding layer. Stainless steel acts as a reinforcing material that imparts shape and strength, and can form a nuclear fuel container with corrosion resistance and impact resistance.
【０００８】硼素化合物としては例えばＢ4Ｃ粉が使用
できる。これを分散含有させる支持体として樹脂は，耐
放射線性を有するプラスチックス材料，例えば，ポリエ
チレン, ポリイミド, ポリエーテルエーテルケトン，フ
ッ化ビニリデンを使用することができる。ステンレス鋼
としてはオーステナイト系ステンレス鋼が好ましい。As the boron compound, for example, B 4 C powder can be used. As the resin for dispersing and containing the resin, a radiation-resistant plastic material such as polyethylene, polyimide, polyetheretherketone, or vinylidene fluoride can be used. As the stainless steel, austenitic stainless steel is preferable.
【０００９】硼素化合物の粒子を分散含有する樹脂層と
ステンレス鋼とを積層するには，ステンレス鋼に該樹脂
層を被覆する方法，或いはステンレス鋼板と該樹脂のフ
イルムまたはシートを接合する方法のいずれによっても
よい。To laminate a resin layer containing particles of a boron compound dispersed therein and stainless steel, either a method of coating the resin layer on stainless steel or a method of joining a stainless steel plate and a film or sheet of the resin is used. May be
【００１０】図１は被覆法を示したものである。多孔板
１を底部にもつ槽２内にプラスチックス粉と硼素化合物
粉を入れ，多孔板１を通じて下方から空気を吹き込むこ
とにより，該粉体を流動状態にする。この流動状態にあ
る粉体中に，予め加熱したステンレス鋼３を浸漬する。
これによって，ステンレス鋼３の表面には，ステンレス
鋼が保有する熱によってプラスチックスが融着すると共
にこれに同伴して硼素化合物粉も付着し，ステンレス鋼
表面には硼素化合物が分散含有した樹脂層が形成され
る。FIG. 1 shows the coating method. Plastic powder and boron compound powder are placed in a tank 2 having a porous plate 1 at the bottom, and air is blown from below through the porous plate 1 to bring the powder into a fluid state. Preheated stainless steel 3 is immersed in the powder in the fluidized state.
As a result, the plastics are fused to the surface of the stainless steel 3 due to the heat of the stainless steel, and the boron compound powder is also attached to the plastics, and the resin layer in which the boron compound is dispersed is contained on the stainless steel surface. Is formed.
【００１１】そのさい，流動させる粉体として，予めプ
ラスチックス粒子内に硼素化合物粒子を含有させた複合
粉を使用することもできる。この場合には，樹脂層中の
硼素化合物濃度を一定にすることができる。また，ステ
ンレス鋼３としては，例えば容器を構成する角管等に加
工したうえで浸漬すれば，加工品の表面に該樹脂層を形
成させることができる。ステンレス鋼３の加熱温度と硼
素化合物粉の濃度は，支持体としての樹脂の種類および
要求される熱中性子遮蔽能によって適切に調節する。At this time, as the powder to be fluidized, it is also possible to use a composite powder in which the boron compound particles are contained in the plastic particles in advance. In this case, the boron compound concentration in the resin layer can be kept constant. In addition, as the stainless steel 3, for example, if it is processed into a square tube or the like forming a container and then immersed, the resin layer can be formed on the surface of the processed product. The heating temperature of the stainless steel 3 and the concentration of the boron compound powder are appropriately adjusted depending on the kind of resin as the support and the required thermal neutron shielding ability.
【００１２】図２は，ステンレス鋼板と該樹脂のシート
を接合した例を示す。すなわち，二枚のステンレス鋼
（SUS304）の板4aと4bの間に硼素化合物粉を含有したポ
リエチレンのシート５をサンドイッチ状に挟み込んだも
のである。この場合には，二枚のステンレス鋼板4aと4b
の間に硼素化合物粉とポリエチレンの粉末との混合粉を
充填したうえで圧着して積層する。得られた積層板を角
管６に加工する。７は溶接部を示している。FIG. 2 shows an example in which a stainless steel plate and a resin sheet are joined together. That is, a polyethylene sheet 5 containing a boron compound powder is sandwiched between two stainless steel (SUS304) plates 4a and 4b. In this case, two stainless steel plates 4a and 4b
A mixed powder of a boron compound powder and a polyethylene powder is filled in the space between them, and then pressure-bonded and laminated. The obtained laminated plate is processed into a square tube 6. Reference numeral 7 indicates a welded portion.
【００１３】図３は，ステンレス鋼板と該樹脂のシート
を接合する他の例を示す。この場合には，ステンレス鋼
の角管８と，硼素化合物粉含有の樹脂シートからなるス
リーブ９を別々に作る。スリーブ９の内径は角管８の外
周長よりも僅かに小さくしておく。そして，スリーブ９
を角管８の外周面に被着させる。そのさい，スリーブ９
は，硼素化合物粉含有の樹脂フイルム１０と，硼素化合
物を含有しない樹脂フイルム１１との積層体とし，後者
のフイルム１１を収縮性のプラスチックス（例えばポリ
エチレン）として，これを角管８との接触面にする。フ
イルム１１の収縮性によって，角管８との密着性が良く
なる。FIG. 3 shows another example of joining a stainless steel plate and a sheet of the resin. In this case, a square tube 8 made of stainless steel and a sleeve 9 made of a resin sheet containing a boron compound powder are separately prepared. The inner diameter of the sleeve 9 is made slightly smaller than the outer peripheral length of the rectangular tube 8. And sleeve 9
Is attached to the outer peripheral surface of the square tube 8. At that time, sleeve 9
Is a laminated body of a resin film 10 containing a boron compound powder and a resin film 11 not containing a boron compound, and the latter film 11 is made into a shrinkable plastic (for example, polyethylene), which is brought into contact with the rectangular tube 8. To face. The contractibility of the film 11 improves the adhesion with the rectangular tube 8.
【００１４】[0014]
【実施例】平均粒径が15μmで純度97％のＢ4Ｃの粒子を
含有させた平均粒径が約100μmのポリエチレン, ポリイ
ミド, ポリエーテルエーテルケトンまたはフッ化ビニリ
デンの複合粉体を，図１に示したように，流動槽内で流
動化させ，SUS304のステンレス鋼板を各樹脂が融着する
に十分な温度に予め加熱したうえで，該流動槽内に浸漬
した。EXAMPLE A composite powder of polyethylene, polyimide, polyetheretherketone or vinylidene fluoride having an average particle size of about 100 μm and containing B 4 C particles having an average particle size of 15 μm and a purity of 97% is shown in FIG. As shown in FIG. 5, the SUS304 stainless steel plate was fluidized in a fluidized tank, preheated to a temperature sufficient for each resin to be fused, and then immersed in the fluidized tank.
【００１５】複合粉体中のＢ4Ｃと樹脂との配合割合
は，Ｂ4Ｃの粉体１kgに対し，ポリエチレンでは３８０
ｇ, ポリイミドでは６００ｇ，ポリエーテルエーテルケ
トンでは６００ｇ，フッ化ビニリデンでは７５０ｇとし
た。ステンレス鋼板の予熱温度は２５０〜３５０℃の範
囲，流動層への浸漬時間は２〜５秒である。流動層から
引き上げたあと，２００〜２２０℃で該塗膜品を２〜３
分間の後加熱を行ったうえで空冷した。The compounding ratio of B 4 C and resin in the composite powder is 380 in polyethylene for 1 kg of B 4 C powder.
g, 600 g for polyimide, 600 g for polyetheretherketone, and 750 g for vinylidene fluoride. The preheating temperature of the stainless steel plate is in the range of 250 to 350 ° C., and the immersion time in the fluidized bed is 2 to 5 seconds. After pulling up from the fluidized bed, the coated product is heated at 200 to 220 ° C. for 2-3 times.
After heating for a minute, it was air-cooled.
【００１６】表１に得られた塗膜品の耐候性, 耐衝撃
性, 加工性, 密着性等の特性評価を示した。表１におい
て，換算Ｂ(wt.%)は熱中性子吸収能が同等なＢ添加ステ
ンレス鋼のＢ量に換算したものである。すなわち, 本発
明の積層体の全厚みと同等な厚みをもつＢ添加ステンレ
ス鋼が示す熱中性子吸収能は，このＢ添加ステンレス鋼
中のＢ含有量に相当するＢを含む本発明の積層体のもの
と等しい。このため，本発明の積層体中に含ませたＢ量
をＢ添加ステンレス鋼中のＢ量に換算した。塗膜厚みが
300μmで2.0wt.%のＢを含有するステンレス鋼に相当す
る。Table 1 shows the evaluation of characteristics such as weather resistance, impact resistance, workability and adhesion of the obtained coating film product. In Table 1, the converted B (wt.%) Is converted to the B content of B-added stainless steel having the same thermal neutron absorption capacity. That is, the thermal neutron absorption capacity of the B-added stainless steel having a thickness equivalent to the total thickness of the laminate of the present invention is the same as that of the laminate of the present invention containing B corresponding to the B content in the B-added stainless steel. Equal to one. Therefore, the amount of B contained in the laminate of the present invention was converted to the amount of B in the B-added stainless steel. Coating thickness
Corresponds to stainless steel containing 2.0 wt.% B at 300 μm.
【００１７】耐候性は耐候性試験 (サンシャインフェザ
ーメーター：2000h, 63℃) にて評価し，耐衝撃性はデ
ュポン衝撃試験, 加工性は２Ｔ折曲げ試験，密着性はエ
リクセン試験を行って評価した。評価基準はＢランク以
上が使用可能と判断して，良いものの順にＡ＞Ｂ＞Ｃの
３ランクとした。熱中性子吸収能は，換算Ｂwt.%のＢを
含むステンレス鋼のものを参考にした。The weather resistance was evaluated by a weather resistance test (sunshine feather meter: 2000h, 63 ° C), the impact resistance was evaluated by a DuPont impact test, the workability by a 2T bending test, and the adhesion by an Erichsen test. .. As an evaluation criterion, it was judged that B rank or higher could be used, and three ranks of A>B> C were given in order of goodness. The thermal neutron absorption capacity is based on stainless steel containing B in the converted Bwt.%.
【００１８】[0018]
【表１】 [Table 1]
【００１９】表1 より，No.3，No.5，No.6，No.8，No.
9, No.11, No.12の材料が, 熱中性子吸収能に優れ, 耐
候性, 耐衝撃性, 加工性, 密着性とも熱中性子遮蔽用の
構造材料として実用上問題のない特性を有していること
わかる。From Table 1, No. 3, No. 5, No. 6, No. 8, No.
The materials No. 9, No. 11 and No. 12 have excellent thermal neutron absorption capacity and have practically no problems as a structural material for thermal neutron shielding in terms of weather resistance, impact resistance, workability and adhesion. I understand.
【００２０】[0020]
【発明の効果】以上説明したように, 本発明によれば好
適な熱中性子遮蔽用材料が得られる。本発明の材料はＢ
含有量を多くしても簡単に製造できる。したがって，従
来のＢ添加ステンレス鋼のように製造性の面からＢ含有
量を大きくできなかったと言う限界を超えることができ
る。このため，肉厚を薄くしても良好な熱中性子吸収能
を持たせることができる。As described above, according to the present invention, a suitable thermal neutron shielding material can be obtained. The material of the present invention is B
It can be easily manufactured even if the content is increased. Therefore, it is possible to exceed the limit that the B content could not be increased from the viewpoint of manufacturability like the conventional B-added stainless steel. For this reason, good thermal neutron absorption capability can be provided even if the wall thickness is reduced.
【００２１】加えて, 強度や形状はステンレス鋼が有す
る強度によって十分に保証され，また耐食性, 耐候性,
耐衝撃性にも優れるから，熱中性子吸収機能に加えて耐
用寿命の点でも優れた核燃料用容器を構成できるし，従
来のＢ添加ステンレス鋼よりも安価であり且つ加工性の
面でも優れる。In addition, the strength and shape are sufficiently ensured by the strength of stainless steel, and the corrosion resistance, weather resistance, and
Since it is also excellent in impact resistance, it can constitute a nuclear fuel container that is excellent in terms of its service life as well as thermal neutron absorption function, and it is cheaper than conventional B-added stainless steel and also excellent in workability.
【００２２】したがって，本発明によれば，核燃料集合
体輸送容器，核燃料保管容器，使用済み核燃料保管容器
などを構成するのに好適な新規且つ安価な熱中性子遮蔽
材料が提供でき，この分野に多大の貢献ができる。Therefore, according to the present invention, it is possible to provide a novel and inexpensive thermal neutron shielding material suitable for constructing a nuclear fuel assembly transportation container, a nuclear fuel storage container, a spent nuclear fuel storage container, etc. Can contribute.
【図１】本発明の積層体の作成方法を説明するための浸
漬槽の略断面図である。FIG. 1 is a schematic cross-sectional view of a dipping tank for explaining a method for producing a laminate of the present invention.
【図２】本発明の積層体の例を示す一部拡大斜視図であ
る。FIG. 2 is a partially enlarged perspective view showing an example of a laminate of the present invention.
【図３】本発明の積層体の作成方法を説明するための一
部拡大斜視図である。FIG. 3 is a partially enlarged perspective view for explaining a method for producing a laminated body of the present invention.
１ 多孔板 ２ 浸漬槽 ３ ステンレス鋼 ４ ステンレス鋼板 ５ 硼素化合物粉含有樹脂層 ６ 積層体からなる角管 ７ 溶接部 ８ ステンレス鋼の角管 ９ 硼素化合物粉含有樹脂のスリーブ １０ 硼素化合物粉含有樹脂フイルム １１ 硼素化合物粉を含有しない樹脂フイルム 1 Perforated Plate 2 Immersion Tank 3 Stainless Steel 4 Stainless Steel Plate 5 Boron Compound Powder-Containing Resin Layer 6 Square Tube Made of Laminate 7 Welded Section 8 Stainless Steel Square Tube 9 Boron Compound Powder-Containing Resin Sleeve 10 Boron Compound Powder-Containing Resin Film 11 Resin film containing no boron compound powder
Claims (3)
せてなる樹脂層と，ステンレス鋼からなる金属層とを積
層してなる熱中性子遮蔽材料。1. A thermal neutron shielding material obtained by laminating a resin layer containing particles of a boron compound dispersedly contained in a resin and a metal layer made of stainless steel.
載の熱中性子遮蔽材料。2. The thermal neutron shielding material according to claim 1, wherein the boron compound is B 4 C.
リエーテルエーテルケトンまたはフッ化ビニリデンから
選ばれたプラスチックスである請求項１または２に記載
の熱中性子遮蔽材料。3. The thermal neutron shielding material according to claim 1, wherein the resin is a plastic selected from polyethylene, polyimide, polyetheretherketone or vinylidene fluoride.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8751592A JPH05256995A (en) | 1992-03-12 | 1992-03-12 | Thermal-neutron shielding material |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8751592A JPH05256995A (en) | 1992-03-12 | 1992-03-12 | Thermal-neutron shielding material |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH05256995A true JPH05256995A (en) | 1993-10-08 |
Family
ID=13917133
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP8751592A Withdrawn JPH05256995A (en) | 1992-03-12 | 1992-03-12 | Thermal-neutron shielding material |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH05256995A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007155499A (en) * | 2005-12-05 | 2007-06-21 | Japan Atomic Energy Agency | Neutron beam shielding structure and method for constructing neutron beam shielding structure |
| CN105729937A (en) * | 2016-01-29 | 2016-07-06 | 南京航空航天大学 | Novel neutron shielding super-hybrid laminate composite material for spent fuel storage and preparation method thereof |
-
1992
- 1992-03-12 JP JP8751592A patent/JPH05256995A/en not_active Withdrawn
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007155499A (en) * | 2005-12-05 | 2007-06-21 | Japan Atomic Energy Agency | Neutron beam shielding structure and method for constructing neutron beam shielding structure |
| CN105729937A (en) * | 2016-01-29 | 2016-07-06 | 南京航空航天大学 | Novel neutron shielding super-hybrid laminate composite material for spent fuel storage and preparation method thereof |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4664881A (en) | Zirconium base fuel cladding resistant to PCI crack propagation | |
| JP2763740B2 (en) | Fuel element and method for improving heat transfer therein | |
| KR20120027034A (en) | High strength multi-layer brazing sheet structures with good controlled atmosphere brazing(cab) brazeability | |
| CA1191624A (en) | Container for the interim and long-term storage of radioactive material | |
| US4115311A (en) | Nuclear waste storage container with metal matrix | |
| JPH0365690A (en) | Corrosion resisting coating for fuel rod | |
| Zhang et al. | Research progress in the preparation of aluminum foam composite structures | |
| JPS5817817B2 (en) | Method for manufacturing large surface area metal bodies | |
| US4031921A (en) | Hydrogen-isotope permeation barrier | |
| JP2014089166A (en) | Neutron absorber and manufacturing method of the same | |
| US4778648A (en) | Zirconium cladded pressurized water reactor nuclear fuel element | |
| US10699819B2 (en) | UF6 transport and process container (30W) for enrichments up to 20% by weight | |
| KR910003286B1 (en) | Composite cladding container for nuclear reactor | |
| JPH0528357B2 (en) | ||
| JP2853133B2 (en) | Cladding plate for structural members of nuclear fuel containers with excellent heat dissipation | |
| JPH0727896A (en) | Storage container for radioactive materials and manufacturing method thereof | |
| Wang et al. | Fabrication and Three‐Point Bending Behavior of Aluminum Foam Sandwich via Controlled Atmosphere Brazing | |
| US3439858A (en) | Brazing composition for carbonaceous materials | |
| CA1168769A (en) | Fuel rod for a nuclear reactor | |
| JP2008082906A (en) | Radioactive material storage container | |
| JP2015230219A (en) | Radiation shield material and nuclear fuel reservoir | |
| CN102672331B (en) | Method for preparing TA2/Q235 composite plate by electric resistance welding and welding material | |
| JPS5841390A (en) | Fuel storage rack for nuclear reactor | |
| US3136051A (en) | Cladding of nuclear fuel elements | |
| US4357985A (en) | Method of isothermally forming a copper base alloy fiber reinforced composite |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 19990518 |