JPS61213695A - Neutron shielding material - Google Patents

Neutron shielding material

Info

Publication number
JPS61213695A
JPS61213695A JP5504285A JP5504285A JPS61213695A JP S61213695 A JPS61213695 A JP S61213695A JP 5504285 A JP5504285 A JP 5504285A JP 5504285 A JP5504285 A JP 5504285A JP S61213695 A JPS61213695 A JP S61213695A
Authority
JP
Japan
Prior art keywords
shielding material
neutron
weight
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.)
Granted
Application number
JP5504285A
Other languages
Japanese (ja)
Other versions
JPH0467640B2 (en
Inventor
哲也 飯田
忠雄 玉村
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

Links

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】 (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。
DETAILED DESCRIPTION OF THE INVENTION (Industrial Application Field) This invention relates to a neutron shielding material with excellent flame retardancy.

(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、パラフィン等が広く用いら
れているが、これらは融点が低い(ポリエチレン=50
〜100℃、パラフィン: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。a湿雰囲気で使用
可能な遮蔽材として、特開昭57−173795号公報
にモノオレフィ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ィン
共重合ゴムioomi部に対して250〜450重Ma
il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。
(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
-100°C, paraffin: 45-60°C), so it cannot be used in a high-temperature atmosphere. They are also flammable and therefore pose a fire hazard. aAs a shielding material that can be used in a humid atmosphere, JP-A-57-173795 discloses a neutron shielding material made from monoolefin copolymer rubber, but the material disclosed here is based on boron compounds (or The amount of lithium compound) added is 250 to 450 weight Ma based on the ioomi part of monoolefin copolymer rubber.
il and very many. 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).

原子力施設においては加速器、Cf−252、Am−B
e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。
At nuclear facilities, accelerators, Cf-252, Am-B
Neutrons from neutron sources such as E and spent fuel 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.

(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づ
゛るものである。
(Purpose of the Invention) This invention was made to solve such conventional problems, and provides a shielding material that has excellent heat resistance and has an excellent shielding effect against neutrons with a hard energy spectrum. It is.

(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。これによっ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っている。
(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 to exhibit its own flame retardant properties, while supplementing its thermal neutron absorption ability with the boron compound.

(実施例) クロロスルホン化ポリエチレンは、802とCQ2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
ースとなっているため、水素原子密度が5〜6X102
2atoms/C13と比較的高密度である。
(Example) Chlorosulfonated polyethylene is a crystalline polymer that has been given elasticity by introducing 802 and CQ2, and because it does not contain unsaturated bonds in the molecule, it is resistant to ozone, oxygen, heat, and oxidizing chemicals. It has very good resistance against It has excellent flame retardancy because it contains chlorine in its molecular structure.
There is also almost no chlorine elution. Also, since it is based on polyethylene, the hydrogen atom density is 5~6X102
It has a relatively high density of 2 atoms/C13.

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(2,5
1(j/cj)が好ましい。何故なら、これは遮蔽材に
所定m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、したがっ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。
Adding a boron compound to chlorosulfonated polyethylene having such properties can improve its ability to absorb thermal neutrons. As this boron compound,
There are boron carbide, boron nitride, boron oxide, etc., but boron carbide (2,5
1(j/cj) is preferred. This is because the addition amount is the smallest in order to give the shielding material a boron atom density of the predetermined m, and therefore the highest hydrogen atom density can be obtained. The particle size of the boron compound is preferably as small as possible in order to enable uniform dispersion in the shielding material, but a center particle size of about 50 μm is sufficiently practical.

上記ホウ素化合物の添加m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3Qcmの厚さの炭素鋼の壁で遮蔽し、その状
態での中性子線m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m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84Gの割合を種々変化させたところ、第1図曲l
111に示すような結果がえられた。すなわち84Cの
添加量が1〜50重量%の範囲内では線量率は0.01
2〜0.025と小さいのに対し、50重量%を超える
と急激に増加する。したがって、84Gの添加間は1〜
50重量%の範囲内に設定する必要がある。
The addition m of the boron compound 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 3Qcm thick carbon steel wall, and the neutron beam rate in that state was calculated. 1, and the neutron beam m rate was calculated in a state where the outside of this carbon steel wall was further shielded with a shielding material with a thickness of 10 cm. In addition, as the above-mentioned shielding material,
When the ratio of 84G added to the basic composition of chlorosulfonated polyethylene was varied, the results were shown in Fig. 1.
The results shown in 111 were obtained. In other words, when the amount of 84C added is within the range of 1 to 50% by weight, the dose rate is 0.01.
While it is small at 2 to 0.025, it increases rapidly when it exceeds 50% by weight. Therefore, between additions of 84G
It is necessary to set it within a range of 50% by weight.

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、カーボンブラック等を配合させて
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、例えばりOロスルホン化ポリエチレン10
0mff1部に対して補強剤(カーボンブラック)20
mff1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。
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 blending amount needs to be small in order to prevent the hydrogen atom density, which is effective in shielding fast neutrons, from decreasing.
0 mff 1 part reinforcing agent (carbon black) 20
It is desirable to use about 1 part of mff, and about 0.5 to 2.0 parts by weight of other parts.

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重口
%、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の核分裂スベク1−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10CI+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(X1Q2
2atog+s/cm3)の数値、ホウ素原子密度は(
x 1020 atoms/cm3 )の数値ヲソレソ
レ示シテいる。
Table 1 shows the amount of boron compound added as a neutron absorber to chlorosulfonated polyethylene in parts by weight, and the ratio of the boron compound is 8.2% by weight for sample 1 and 1.2% by weight for sample 2. This corresponds to 8% by weight. Regarding these shielding materials, a neutron source with a nuclear fission magnitude of uranium-235 is shielded by a 30 cm thick carbon steel wall, and the neutron dose rate in that state is set to 1. The figure shows the results of calculating the neutron dose rate in a state where the outside of the wall of the cell is shielded with the above-mentioned shielding material having a thickness of 10CI+. In addition, in the same table, the hydrogen atom density is (X1Q2
2atog+s/cm3), the boron atom density is (
x 1020 atoms/cm3).

第1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。
As is clear from the above table in Table 1, all the 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.

(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、これによってクロロスルホン
化ポリエチレンの特性を生かしつつ、中性子遮蔽性能の
向上を図ったものであり、M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
プラスチック製中性子遮蔽材を使用できなかった箇所に
使用可能である。
(Effects of the Invention) As explained above, the present invention uses chlorosulfonated polyethylene as a material and blends 1 to 50% by weight of a boron compound therein, thereby making the most of the characteristics of chlorosulfonated polyethylene. This product has improved neutron shielding performance, and due to its excellent flammability, it can be used in places where there is a risk of fire or high temperatures, where conventional plastic neutron shielding materials cannot be used. Available for use.

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

図面は84Gの添加量とIIfIL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 84G added and the IIfIL 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. A neutron shielding material made of chlorosulfonated polyethylene and containing 1 to 50% by weight of a boron compound.
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 true JPS61213695A (en) 1986-09-22
JPH0467640B2 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)

Cited By (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
JP2005512101A (en) * 2001-12-12 2005-04-28 コジュマ・ロジスティクス Materials based on vinyl ester resins for neutron shielding and subcritical maintenance
JP2011058934A (en) * 2009-09-09 2011-03-24 Japan Atomic Energy Agency Neutron absorption sheet

Citations (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

Patent Citations (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

Cited By (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
JP2005512101A (en) * 2001-12-12 2005-04-28 コジュマ・ロジスティクス Materials based on vinyl ester resins for neutron shielding and subcritical maintenance
JP2011058934A (en) * 2009-09-09 2011-03-24 Japan Atomic Energy Agency Neutron absorption sheet

Also Published As

Publication number Publication date
JPH0467640B2 (en) 1992-10-28

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