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JPH0467640B2 - - Google Patents
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JPH0467640B2 - - Google Patents

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Publication number
JPH0467640B2
JPH0467640B2 JP60055042A JP5504285A JPH0467640B2 JP H0467640 B2 JPH0467640 B2 JP H0467640B2 JP 60055042 A JP60055042 A JP 60055042A JP 5504285 A JP5504285 A JP 5504285A JP H0467640 B2 JPH0467640 B2 JP H0467640B2
Authority
JP
Japan
Prior art keywords
neutron
weight
shielding material
boron
shielding
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 - Lifetime
Application number
JP60055042A
Other languages
Japanese (ja)
Other versions
JPS61213695A (en
Inventor
Tetsuya Iida
Tadao Tamamura
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.)
Kobe Steel Ltd
Original Assignee
Kobe Steel 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 Kobe Steel Ltd filed Critical Kobe Steel Ltd
Priority to JP5504285A priority Critical patent/JPS61213695A/en
Publication of JPS61213695A publication Critical patent/JPS61213695A/en
Publication of JPH0467640B2 publication Critical patent/JPH0467640B2/ja
Granted legal-status Critical Current

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  • Compositions Of Macromolecular Compounds (AREA)
  • Absorbent Articles And Supports Therefor (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Particle Accelerators (AREA)

Description

【発明の詳細な説明】[Detailed description of the invention]

(産業上の利用分野) この発明は難燃性の優れた中性子遮蔽材に関す
るものである。 (従来技術) 従来より原子炉等で使用される中性子遮蔽材と
して水素含有量の多いポリエチレン、パラフイン
等が広く用いられているが、これらは融点が低い
(ポリエチレン:50〜100℃、パラフイン:45〜60
℃)ため、高温雰囲気では使用することができな
い。またこれらは可燃性であるために、火災の危
険性もある。高温雰囲気で使用可能な遮蔽材とし
て、特開昭57−173795号公報にモノオレフイン共
重合ゴムを素材とする中性子遮蔽材が示されてい
るが、ここで開示された材料はホウ素化合物(ま
たはリチウム化合物)の添加量がモノオレフイン
共重合ゴム100重量部に対して250〜450重量部と
非常に多い。これは熱中性子の優勢な所で使用す
る場合には有効であるが、中性子エネルギーが高
い(スペクトルが硬い)場合には逆に性能の低い
ものとなる。 原子力施設においては加速器、Cf−252、Am
−Be等の中性子源や使用済燃料等からの中性子
はエネルギースペクトルが硬く、このようなもの
に対する遮蔽材として有効で、耐熱性の優れた遮
蔽材の開発が望まれていた。 (発明の目的) この発明は、このような従来の課題の解決のた
めになされたものであり、耐熱性が優れ、エネル
ギースペクトルが硬い中性子に対する遮蔽効果の
優れた遮蔽材を提供するものである。 (発明の構成) この発明は、クロロスルホン化ポリエチレンを
素材とし、これにホウ素化合物を1〜50重量%配
合したものである。これによつてクロロスルホン
化ポリエチレン自体の難燃性を発揮させるととも
に、ホウ素化合物により熱中性子吸収能力を補つ
ている。 (実施例) クロロスルホン化ポリエチレンは、SO2とCl2
とを導入して弾性を与えた結晶性のポリマーであ
り、分子内に不飽和結合を含まないためにオゾ
ン、酸素、熱および酸化性薬品に対して抵抗性が
非常に良好である。分子構造として塩素を含んで
いるために難燃性に優れており、また塩素の溶出
もほとんどない。またポリエチレンがベースとな
つているため、水素原子密度が5〜6×
1022atoms/cm3と比較的高密度である。 このような性質のクロロスルホン化ポリエチレ
ンに対してホウ素化合物を加えると、熱中性子を
吸収する能力を向上させることができる。このホ
ウ素化合物としては、炭化ホウ素、窒化ホウ素、
酸化ホウ素等があるが、添加物としてはこの中で
最も密度の高い炭化ホウ素(2.51g/cm3)が好ま
しい。何故なら、これは遮蔽材に所定量のホウ素
原子密度を与えるのに添加量が最も少なくてす
み、したがつて水素原子密度の最も高いものが得
られるためである。ホウ素化合物の粒径は、遮蔽
材の中での均一な分散を可能にするために、でき
るだけ小さい方が望ましいが、中心粒径50μm程
度でも十分に実用可能である。 上記ホウ素化合物の添加量は、遮蔽材が使用さ
れる場所の中性子エネルギースペクトルに対応し
て設定すればよい。ホウ素化合物の添加量とその
効果との関係を調べるために、ウラン235の核分
裂スペクトルを持つ中性子の線源を30cmの厚さの
炭素鋼の壁で遮蔽し、その状態での中性子線量率
を1とし、さらにこの炭素鋼の壁の外側を10cmの
厚さの遮蔽材で遮蔽した状態において中性子線量
率を計算した。なお、上記遮蔽材としては、クロ
ロスルホン化ポリエチレンの基本組成に対して添
加するB4Cの割合を種々変化させたところ、第1
図曲線1に示すような結果がえられた。すなわち
B4Cの添加量が1〜50重量%の範囲内では線量率
は0.012〜0.025と小さいのに対し、50重量%を超
えると急激に増加する。したがつて、B4Cの添加
量は1〜50重量%の範囲内に設定する必要があ
る。 また上記材料にゴムとしての機械的強度、性状
を向上させるために架橋助剤、カーボンブラツク
等を配合させてもよい。その配合量は、高速中性
子の遮蔽に有効である水素原子密度が低下しない
ようにするために少量にする必要があり、例えば
クロロスルホン化ポリエチレン100重量部に対し
て補強剤(カーボンブラツク)20重量部程度、そ
の他については0.5〜2.0重量部程度が望ましい。 第1表は、クロロスルホン化ポリエチレンに対
して中性子吸収材としてホウ素化合物を加えたも
のを重量部で示しており、ホウ素化合物の比率は
試料1では8.2重量%、試料2では1.8重量%に相
当する。またこれらの遮蔽材について、ウラン
235の核分裂スペクトルを持つ中性子の線源を30
cmの厚さの炭素鋼の壁で遮蔽し、その状態での中
性子線量率を1とし、さらにこの炭素鋼の壁の外
側を10cmの厚さの上記遮蔽材で遮蔽した状態にお
いて中性子線量率を計算した結果を示している。
なお、同表において、水素原子密度は(×
1022atoms/cm3)の数値、ホウ素原子密度は(×
1020atoms/cm3)の数値をそれぞれ示している。
(Industrial Application Field) This invention relates to a neutron shielding material with excellent flame retardancy. (Prior art) Polyethylene, paraffin, etc. with high hydrogen content have been widely used as neutron shielding materials used in nuclear reactors, etc., but these have low melting points (polyethylene: 50 to 100 °C, paraffin: 45 ~60
℃), so it cannot be used in high-temperature atmospheres. They are also flammable and therefore pose a fire hazard. As a shielding material that can be used in high-temperature atmospheres, Japanese Patent Application Laid-Open No. 173795/1983 discloses a neutron shielding material made from monoolefin copolymer rubber. The amount of compound (compound) added is extremely large at 250 to 450 parts by weight per 100 parts by weight of monoolefin copolymer rubber. This is effective when used in a place where thermal neutrons are dominant, but the performance becomes poor when the neutron energy is high (the spectrum is hard). In nuclear facilities, accelerators, Cf-252, Am
Neutrons from neutron sources such as -Be, spent fuel, etc. have hard energy spectra, and it has been desired to develop a shielding material that is effective as a shielding material against such materials and has excellent heat resistance. (Purpose of the Invention) This invention was made to solve such conventional problems, and provides a shielding material that has excellent heat resistance and an excellent shielding effect against neutrons with a hard energy spectrum. . (Structure of the Invention) This invention uses chlorosulfonated polyethylene as a material, and blends 1 to 50% by weight of a boron compound therein. This allows the chlorosulfonated polyethylene itself to exhibit its flame retardant properties, while supplementing its thermal neutron absorption ability with the boron compound. (Example) Chlorosulfonated polyethylene contains SO 2 and Cl 2
It is a crystalline polymer that has been given elasticity through the introduction of molecule, and because it does not contain unsaturated bonds in its molecules, it has very good resistance to ozone, oxygen, heat, and oxidizing chemicals. Because it contains chlorine in its molecular structure, it has excellent flame retardancy, and almost no chlorine elutes. Also, since it is based on polyethylene, the hydrogen atom density is 5 to 6×
It has a relatively high density of 10 22 atoms/cm 3 . Adding a boron compound to chlorosulfonated polyethylene having such properties can improve its ability to absorb thermal neutrons. These boron compounds include boron carbide, boron nitride,
Although there are boron oxide and the like, boron carbide (2.51 g/cm 3 ), which has the highest density among them, is preferable as an additive. This is because it requires the smallest amount of addition to provide the shielding material with a predetermined amount of boron atom density, and thus provides the highest hydrogen atom density. The particle size of the boron compound is preferably as small as possible in order to enable uniform dispersion within the shielding material, but a center particle size of about 50 μm is sufficiently practical. The amount of the boron compound added may be set in accordance with the neutron energy spectrum of the location where the shielding material is used. In order to investigate the relationship between the amount of boron compounds added and their effects, a neutron source with the fission spectrum of uranium-235 was shielded with a 30 cm thick carbon steel wall, and the neutron dose rate in that state was reduced to 1. Then, the neutron dose rate was calculated with the outside of this carbon steel wall shielded with a 10 cm thick shielding material. In addition, as for the above-mentioned shielding material, when the ratio of B 4 C added to the basic composition of chlorosulfonated polyethylene was varied, the first
The results shown in curve 1 in the figure were obtained. i.e.
When the amount of B 4 C added is within the range of 1 to 50% by weight, the dose rate is as small as 0.012 to 0.025, but when it exceeds 50% by weight, it increases rapidly. Therefore, the amount of B 4 C added must be set within the range of 1 to 50% by weight. Furthermore, a crosslinking aid, carbon black, etc. may be added to the above material in order to improve the mechanical strength and properties of the rubber. The amount of the reinforcing agent (carbon black) needs to be small in order to prevent the hydrogen atom density, which is effective in shielding fast neutrons, from decreasing. About 0.5 to 2.0 parts by weight is desirable for other parts. Table 1 shows the amount of boron compound added as a neutron absorber to chlorosulfonated polyethylene in parts by weight, and the proportion of boron compound is equivalent to 8.2% by weight in sample 1 and 1.8% by weight in sample 2. do. In addition, regarding these shielding materials, uranium
30 neutron sources with a fission spectrum of 235
The neutron dose rate is set to 1 when shielded by a carbon steel wall with a thickness of cm, and the neutron dose rate is set to 1 when the outside of this carbon steel wall is shielded with the above shielding material with a thickness of 10 cm. The calculated results are shown.
In addition, in the same table, the hydrogen atom density is (×
10 22 atoms/cm 3 ), the boron atom density is (×
10 20 atoms/cm 3 ).

【表】 上記表から明らかなように、いずれの試料にお
いても中性子遮蔽性能は良好であり、また難燃性
の指標となる酸素指数も充分高く、難燃性に優れ
ていることがわかる。 (発明の効果) 以上説明したように、この発明はクロロスルホ
ン化ポリエチレンを素材とし、これにホウ素化合
物を1〜50重量%配合したものであり、これによ
つてクロロスルホン化ポリエチレンの特性を生か
しつつ、中性子遮蔽性能の向上を図つたものであ
り、難燃性が優れているために火災の恐れのある
場所、温度が高くなる場所等の、従来のプラスチ
ツク製中性子遮蔽材を使用できなかつた箇所に使
用可能である。
[Table] As is clear from the above table, all samples had good neutron shielding performance, and the oxygen index, which is an indicator of flame retardancy, was sufficiently high, indicating that they had excellent flame retardancy. (Effects of the Invention) As explained above, the present invention uses chlorosulfonated polyethylene as a material and contains 1 to 50% by weight of a boron compound, thereby taking advantage of the characteristics of chlorosulfonated polyethylene. At the same time, it is designed to improve neutron shielding performance, and because of its excellent flame retardant properties, it can be used in places where there is a risk of fire or where the temperature is high, where conventional plastic neutron shielding materials cannot be used. It can be used in places.

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

図面はB4Cの添加量と線量率との関係を示す特
性図である。 1……特性曲線。
The drawing is a characteristic diagram showing the relationship between the amount of B 4 C added and the dose rate. 1...Characteristic curve.

Claims (1)

【特許請求の範囲】[Claims] 1 クロロスルホン化ポリエチレンを素材とし、
これにホウ素化合物を1〜50重量%配合すること
を特徴とする中性子遮蔽材。
1 Made from chlorosulfonated polyethylene,
A neutron shielding material characterized in that 1 to 50% by weight of a boron compound is blended therein.
JP5504285A 1985-03-19 1985-03-19 Neutron shielding material Granted JPS61213695A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP5504285A JPS61213695A (en) 1985-03-19 1985-03-19 Neutron shielding material

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP5504285A JPS61213695A (en) 1985-03-19 1985-03-19 Neutron shielding material

Publications (2)

Publication Number Publication Date
JPS61213695A JPS61213695A (en) 1986-09-22
JPH0467640B2 true JPH0467640B2 (en) 1992-10-28

Family

ID=12987606

Family Applications (1)

Application Number Title Priority Date Filing Date
JP5504285A Granted JPS61213695A (en) 1985-03-19 1985-03-19 Neutron shielding material

Country Status (1)

Country Link
JP (1) JPS61213695A (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP3003656U (en) * 1994-04-28 1994-10-25 株式会社アスク Neutron shielding duct device
FR2833402B1 (en) * 2001-12-12 2004-03-12 Transnucleaire NEUTRONIC SHIELDING AND SUB-CRITICITY MAINTAINING MATERIAL BASED ON VINYLESTER RESIN
JP5609048B2 (en) * 2009-09-09 2014-10-22 独立行政法人日本原子力研究開発機構 Neutron beam absorbing sheet

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS56131649A (en) * 1980-03-21 1981-10-15 Showa Denko Kk Neutron shield

Also Published As

Publication number Publication date
JPS61213695A (en) 1986-09-22

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