JPH07138044A - Transparent neutron shielding glass - Google Patents

Transparent neutron shielding glass

Info

Publication number
JPH07138044A
JPH07138044A JP28333493A JP28333493A JPH07138044A JP H07138044 A JPH07138044 A JP H07138044A JP 28333493 A JP28333493 A JP 28333493A JP 28333493 A JP28333493 A JP 28333493A JP H07138044 A JPH07138044 A JP H07138044A
Authority
JP
Japan
Prior art keywords
weight
neutron shielding
glass
transparent
rays
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
JP28333493A
Other languages
Japanese (ja)
Inventor
Yoshifumi Harada
恵文 原田
Hisashi Okuda
久志 奥田
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.)
Ask Corp
Original Assignee
Ask Corp
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 Ask Corp filed Critical Ask Corp
Priority to JP28333493A priority Critical patent/JPH07138044A/en
Publication of JPH07138044A publication Critical patent/JPH07138044A/en
Pending legal-status Critical Current

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Classifications

    • CCHEMISTRY; METALLURGY
    • C03GLASS; MINERAL OR SLAG WOOL
    • C03CCHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
    • C03C3/00Glass compositions
    • C03C3/04Glass compositions containing silica
    • C03C3/076Glass compositions containing silica with 40% to 90% silica, by weight
    • C03C3/089Glass compositions containing silica with 40% to 90% silica, by weight containing boron
    • C03C3/091Glass compositions containing silica with 40% to 90% silica, by weight containing boron containing aluminium
    • CCHEMISTRY; METALLURGY
    • C03GLASS; MINERAL OR SLAG WOOL
    • C03CCHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
    • C03C4/00Compositions for glass with special properties
    • C03C4/08Compositions for glass with special properties for glass selectively absorbing radiation of specified wave lengths

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  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Materials Engineering (AREA)
  • Organic Chemistry (AREA)
  • Glass Compositions (AREA)

Abstract

PURPOSE:To obtain neutron shielding glass capable of adding lithium in an inexpensive shape and excellent in transparency. CONSTITUTION:This transparent neutron shielding glass contains 55-70wt.% of SiO2, 3-15wt.% of Al2O3, 10-20wt.% of Li2O, 5-15wt.% of B2O3 and 1-4wt.% of CaO+MgO.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、原子力研究施設、同位
体実験室、再処理施設等の放射線遮蔽ガラス窓等に使用
される透明中性子遮蔽ガラスに関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a transparent neutron shielding glass used for radiation shielding glass windows in nuclear research facilities, isotope laboratories, reprocessing facilities and the like.

【0002】[0002]

【従来の技術】合成樹脂に、酸化鉛、ハロゲン化鉛、酢
酸鉛等の鉛化合物を含有せしめて、軽量で加工性、成形
性に富む放射線遮蔽材料が得られることは公知である。
しかし、透明性を有し、硬質の熱可塑性樹脂に、上述の
ような鉛化合物を含有せしめて、実質上満足な放射線遮
蔽能を有する材料は、しばしばその透明性を失い、ま
た、ブリード現象を起こしたり、脆弱になるなど実質上
種々の問題を有する。
2. Description of the Related Art It is known that a radiation shielding material having a light weight and excellent workability and moldability can be obtained by incorporating a lead compound such as lead oxide, lead halide or lead acetate into a synthetic resin.
However, a material having a transparent and hard thermoplastic resin containing a lead compound as described above and having a substantially satisfactory radiation shielding ability often loses its transparency and causes a bleeding phenomenon. It causes various problems such as wakeup and fragility.

【0003】この問題を解決するために、例えば特開昭
53−9994号公報には、(A)メタクリル酸メチルまたはス
チレンのうち少なくとも1種のモノマーを必須成分とし
て含み、熱変形温度65℃以上を有し、かつ厚さ8mm
で測定した全光線透過率が70%以上である重合体、ポ
リカーボネート、ポリ塩化ビニルよりなる群から選ばれ
た熱可塑性重合体35〜87重量%、及び(B)一般式
(RCOO)aPb(ただし、aは鉛の原子価に等しい整
数、Rは炭素数5〜20の飽和もしくは不飽和の炭化水
素を表す)で表される有機酸鉛65〜13重量%からな
る放射線遮蔽用組成物が開示されている。
To solve this problem, for example, Japanese Patent Laid-Open No.
JP-A-53-9994 contains (A) at least one monomer of methyl methacrylate or styrene as an essential component, has a heat distortion temperature of 65 ° C. or higher, and has a thickness of 8 mm.
35 to 87% by weight of a thermoplastic polymer selected from the group consisting of a polymer having a total light transmittance of 70% or more, a polycarbonate, and polyvinyl chloride measured by (B) general formula
(RCOO) a Pb (provided that a is an integer equal to the valence of lead and R is a saturated or unsaturated hydrocarbon having 5 to 20 carbon atoms) and is composed of 65 to 13% by weight of lead organic acid. Radiation shielding compositions are disclosed.

【0004】しかし、上述の放射線遮蔽用組成物は、X
線やγ線のような電磁波及びα線、β線のような荷電粒
子に対しては有効な遮蔽能力を示す鉛が配合されている
ものの、熱中性子線に対しては不充分なものである。
However, the above-mentioned radiation shielding composition is
Although it contains lead that shows effective shielding ability against electromagnetic waves such as gamma rays and gamma rays and charged particles such as alpha rays and beta rays, it is insufficient for thermal neutron rays. .

【0005】一方、中性子線遮蔽の高分子材料として、
ポリエチレンまたはメタクリル樹脂に硼素化合物を添加
することも知られている。しかし、この方法も中性子線
吸収能は大きいものの、中性子吸収反応に伴い生成する
ヘリウム、リチウムは中性子吸収能がほとんどないた
め、中性子の吸収量の増加を伴わないその能力は減少し
ていく傾向をもつと共に、光学的及び機械的性質につい
て満足すべきところまで至っていない。
On the other hand, as a polymer material for shielding neutron rays,
It is also known to add boron compounds to polyethylene or methacrylic resins. However, this method also has a large neutron absorption capacity, but since helium and lithium generated by the neutron absorption reaction have almost no neutron absorption capacity, their capacity does not tend to decrease without increasing the absorption amount of neutrons. In addition, the optical and mechanical properties have not yet been satisfied.

【0006】中性子線を吸収する物質として上記の硼素
化合物以外に、原子番号62、63及び64の希土類元
素であるサマリウム、ユーロピウム及びガドリニウムが
熱中性子線の吸収能が硼素よりも更に大きいことが知ら
れている。このような成分が配合された組成物としては
例えば特開昭60−99150号公報に、可視領域においてメ
タクリル樹脂を除く透明な熱可塑性樹脂及び/または熱
硬化性樹脂からなる樹脂にガドリニウム、サマリウムま
たはユーロピウムの少なくとも1種からなる希土類元素
化合物を均一に分散し溶解してなる樹脂組成物が開示さ
れている。
In addition to the above-mentioned boron compounds as substances that absorb neutron rays, it is known that samarium, europium and gadolinium, which are rare earth elements with atomic numbers 62, 63 and 64, have a higher absorption capacity for thermal neutron rays than boron. Has been. As a composition containing such components, for example, in JP-A-60-99150, gadolinium, samarium or a resin made of a transparent thermoplastic resin and / or a thermosetting resin excluding methacrylic resin in the visible region is used. A resin composition is disclosed in which a rare earth element compound composed of at least one of europium is uniformly dispersed and dissolved.

【0007】しかし、上記特開昭60−99150号公報に開
示された樹脂組成物には、ガドリニウム等の希土類元素
化合物が全樹脂分に対して希土類元素として0.001
〜10重量%の範囲でしか添加配合されていない。この
理由は、配合量が10重量%を超えると樹脂組成物の機
械的性質及び透明性が損なわれるためである。しかし、
上記上限量の希土類元素を添加配合した樹脂組成物でも
中性子線吸収能は充分とは言えず、良好な性能を有する
透明放射線遮蔽材とは言えない。
However, in the resin composition disclosed in the above-mentioned JP-A-60-99150, a rare earth element compound such as gadolinium is added as a rare earth element in the total resin content of 0.001.
Only 10 to 10% by weight is added and compounded. The reason for this is that if the blending amount exceeds 10% by weight, the mechanical properties and transparency of the resin composition are impaired. But,
Even the resin composition containing the above-mentioned upper limit amount of the rare earth element added cannot be said to have sufficient neutron absorption capacity, and cannot be said to be a transparent radiation shielding material having good performance.

【0008】そこで、本発明者らは、ガドリニウム塩を
ガドリニウム換算量で10〜30重量%、前記ガドリニ
ウム塩を溶解するためのアミン系溶剤またはアミド系溶
剤0.2〜20重量%、樹脂40〜70重量%及び反応
開始剤0.01〜1重量%よりなる透明放射線遮蔽材並
びにガドリニウム塩をガドリニウム換算量で10〜30
重量%、鉛塩を鉛換算量で20重量%以下、ガドリニウ
ム換算量及び鉛換算量でのガドリニウム塩と鉛塩の合計
量30重量%以下、前記ガドリニウム塩及び鉛塩を溶解
するためのアミン系溶剤またはアミド系溶剤0.2〜2
0重量%、樹脂40〜70重量%及び反応開始剤0.0
1〜1重量%よりなる透明放射線遮蔽材を既に提唱して
いる(特願平4−74408号)。
Therefore, the present inventors have found that the gadolinium salt is 10 to 30% by weight in terms of gadolinium, the amine or amide solvent is 0.2 to 20% by weight for dissolving the gadolinium salt, and the resin is 40 to 40% by weight. A transparent radiation shielding material comprising 70% by weight and a reaction initiator of 0.01 to 1% by weight, and a gadolinium salt in an amount of 10 to 30 in terms of gadolinium.
% By weight, lead salt is 20% by weight or less in terms of lead, gadolinium equivalent amount and total amount of gadolinium salt and lead salt in terms of lead are 30% by weight or less, amine system for dissolving the gadolinium salt and lead salt Solvent or amide solvent 0.2-2
0% by weight, resin 40 to 70% by weight and reaction initiator 0.0
A transparent radiation shielding material consisting of 1 to 1% by weight has already been proposed (Japanese Patent Application No. 4-74408).

【0009】しかし、上述のような樹脂系の透明放射線
遮蔽材は、その製造過程などにおいて、人体に影響を及
ぼす恐れのある成分、溶剤等を使用するため、安全性が
必ずしも充分とは言えない。
However, the resin-based transparent radiation shielding material as described above does not always have sufficient safety because it uses components, solvents, etc. which may affect the human body in the manufacturing process thereof. .

【0010】また、特公平5−30776号公報には、Si
2:35〜56重量%、PbO:24〜46重量%、
Li2O:0〜2.5重量%、Na2O:0〜4重量%、
2O:7〜21重量%、Cs2O:0〜5重量%(ただ
し、Na2O+K2O+Cs2Oの合計量は12〜21重
量%)、CeO2:0.5〜2.5重量%、CuO+Fe2
3:0〜0.05重量%のガラス系において、該ガラス
系はMgO、CaO、SrO、BaO、ZnO及びCd
Oを含まず、かつSiO2が少なくとも35%含まれて
いることを条件にB23及びGd23で置換されてな
り、高エネルギー放射線に対する耐放電性が5×108
を越えることを特徴とするγ線、X線及び中性子線を吸
収する放射線遮蔽ガラスが開示されている。また、該公
報には、中性子を吸収する目的で、付加的にLi−6を
(Li−6)2Oの形で2.4重量%未満の量で添加できる
ことも開示されている。
Further, Japanese Patent Publication No. 5-30776 discloses that Si
O 2: 35~56 weight%, PbO: 24~46% by weight,
Li 2 O: 0 to 2.5% by weight, Na 2 O: 0 to 4% by weight,
K 2 O: 7 to 21 wt%, Cs 2 O: 0 to 5 wt% (provided that the total amount of Na 2 O + K 2 O + Cs 2 O is 12 to 21 wt%), CeO 2: 0.5 to 2.5 % By weight, CuO + Fe 2
O 3: at 0-0.05% by weight of the glass-based, the glass system MgO, CaO, SrO, BaO, ZnO and Cd
It is replaced by B 2 O 3 and Gd 2 O 3 provided that it does not contain O and contains at least 35% of SiO 2 , and has discharge resistance to high energy radiation of 5 × 10 8
A radiation-shielding glass that absorbs γ-rays, X-rays, and neutron rays, which is characterized by exceeding the above range, is disclosed. Further, in the publication, Li-6 is additionally added for the purpose of absorbing neutrons.
It is also disclosed that it can be added in the form of (Li-6) 2 O in an amount of less than 2.4% by weight.

【0011】[0011]

【発明が解決しようとする課題】しかし、上記公報に開
示された放射線遮蔽ガラスは、X線やγ線のような電磁
波及びα線、β線のような荷電粒子に対しては有効な遮
蔽能力を示す鉛がPbOとして24〜46重量%も含ま
れており、中性子を遮蔽する目的で添加されているリチ
ウムは非常に高価であるLi−6であり、原子力研究施
設や再処理施設などの放射線遮蔽ガラス窓として大量に
使用するには不適であるという問題点がある。また、該
公報においては、SiO2が35重量%含まれていると
いう条件で、B23やGd23で置換できる旨も開示さ
れているが、一般にSiO2含量が35重量%程度と比
較的少ない場合には、製造の際のガラス化段階で結晶化
が進み易く、結晶化が進むと透明性が損なわれるという
問題点も生ずる。
However, the radiation shielding glass disclosed in the above publication has an effective shielding ability against electromagnetic waves such as X-rays and γ-rays and charged particles such as α-rays and β-rays. The lead, which is shown as PbO, is contained in an amount of 24 to 46% by weight, and the lithium added for the purpose of shielding neutrons is Li-6, which is very expensive. There is a problem that it is not suitable for use in large quantities as a shielding glass window. The publication also discloses that B 2 O 3 and Gd 2 O 3 can be substituted under the condition that SiO 2 is contained in an amount of 35% by weight, but generally, the SiO 2 content is about 35% by weight. When the amount is relatively small, crystallization is likely to proceed in the vitrification stage during production, and there is a problem that transparency is impaired as crystallization proceeds.

【0012】従って、本発明の目的は、安価な形態でリ
チウムを添加することができる透明性に優れた中性子遮
蔽ガラスを提供することにある。
[0012] Therefore, an object of the present invention is to provide a neutron shielding glass having excellent transparency, to which lithium can be added in an inexpensive form.

【0013】[0013]

【課題を解決するための手段】即ち、本発明の透明中性
子遮蔽ガラスは、SiO2:55〜70重量%、Al2
3:3〜15重量%、Li2O:10〜20重量%、B2
3:5〜15重量%及びCaO+MgO:1〜4重量
%を含有してなるガラスからなることを特徴とする。
That is, the transparent neutron shielding glass of the present invention comprises: SiO 2 : 55 to 70% by weight, Al 2 O
3 : 3 to 15% by weight, Li 2 O: 10 to 20% by weight, B 2
O 3: 5 to 15 wt% and CaO + MgO: characterized by comprising the glass comprising from 1 to 4 wt%.

【0014】[0014]

【作用】本発明の透明中性子遮蔽ガラスは、中性子遮蔽
能力のみを有するガラスを安価に提供するために、中性
子吸収能を有するリチウムを安価な形態で配合したもの
である。なお、X線やγ線のような電磁波及びα線、β
線のような荷電粒子に対しては有効な遮蔽能力を示す鉛
を配合することが必要な場合には、鉛含有ガラスを併用
して使用すれば特に問題はない。
The transparent neutron shielding glass of the present invention contains lithium having a neutron absorbing ability in an inexpensive form in order to inexpensively provide a glass having only a neutron shielding ability. It should be noted that electromagnetic waves such as X-rays and γ-rays and α-rays and β-rays
When it is necessary to mix lead that exhibits an effective shielding ability with respect to charged particles such as rays, there is no particular problem if lead-containing glass is used in combination.

【0015】本発明の透明中性子遮蔽ガラスにおいて、
SiO2の配合量は55〜70重量%の範囲内である。
SiO2の配合量が55重量%未満の場合には、透明性
が悪くなるために好ましくなく、また、70重量%を超
えると中性子遮蔽能を有する成分の添加量が減少するた
めに好ましくない。
In the transparent neutron shielding glass of the present invention,
The blending amount of SiO 2 is in the range of 55 to 70% by weight.
When the content of SiO 2 is less than 55% by weight, the transparency is deteriorated, which is not preferable, and when it exceeds 70% by weight, the amount of the component having the neutron shielding ability is decreased, which is not preferable.

【0016】また、本発明の透明中性子遮蔽ガラスにお
いて、Al23の配合量は3〜15重量%の範囲内であ
る。Al23の配合量が3重量%未満の場合には、物理
特性に悪影響を及ぼすために好ましくなく、また、15
重量%を超えると中性子遮蔽能を有する成分の添加量が
減少するために好ましくない。
In the transparent neutron shielding glass of the present invention, the compounding amount of Al 2 O 3 is within the range of 3 to 15% by weight. When the content of Al 2 O 3 is less than 3% by weight, the physical properties are adversely affected, which is not preferable.
If it exceeds 5% by weight, the addition amount of the component having the neutron shielding ability decreases, which is not preferable.

【0017】更に、本発明の透明中性子遮蔽ガラスにお
いて、Li2Oの配合量は10〜20重量%の範囲内で
ある。Li2Oの配合量が10重量%未満の場合には、
熱中性子の遮蔽能力が充分でないために好ましくなく、
また、20重量%を超えると透明性に悪影響を及ぼすた
めに好ましくない。ここで、本発明において使用される
Li成分は熱中性子遮蔽能と共に高速中性子遮蔽能をも
有し、熱中性子遮蔽能のみを有するB成分等とは異なる
挙動を示す。なお、Li2Oは、Li2CO3、Li(O
H)等の形態で配合することができる。
Further, in the transparent neutron shielding glass of the present invention, the compounding amount of Li 2 O is within the range of 10 to 20% by weight. When the content of Li 2 O is less than 10% by weight,
It is not preferable because the thermal neutron shielding ability is not sufficient,
Further, if it exceeds 20% by weight, the transparency is adversely affected, which is not preferable. Here, the Li component used in the present invention has a fast neutron shielding ability as well as a thermal neutron shielding ability, and exhibits a behavior different from that of the B component or the like having only the thermal neutron shielding ability. In addition, Li 2 O is Li 2 CO 3 , Li (O
H) and the like.

【0018】また、本発明の透明中性子遮蔽ガラスにお
いて、B23の配合量は5〜15重量%の範囲内であ
る。B23の配合量が5重量%未満の場合には、熱中性
子の遮蔽能力が充分でないために好ましくなく、また、
15重量%を超えるとLi成分との合計量の上限は他の
配合成分との関係でおのずと決まってくるために、Li
成分の添加量が減少するために好ましくない。
In the transparent neutron shielding glass of the present invention, the compounding amount of B 2 O 3 is in the range of 5 to 15% by weight. When the content of B 2 O 3 is less than 5% by weight, the thermal neutron shielding ability is insufficient, which is not preferable.
If it exceeds 15% by weight, the upper limit of the total amount of the Li component is naturally determined in relation to the other compounding components, so that Li
It is not preferable because the added amount of the component is reduced.

【0019】更に、本発明の透明中性子遮蔽ガラスに
は、成形助剤としてCaO及び/またはMgOを配合す
る。CaOとMgOの配合量は合計量で1〜4重量%の
範囲内である。該配合量が1重量%未満の場合には、添
加効果が現れないために好ましくなく、また、4重量%
を超えると透明性に悪影響を及ぼすために好ましくな
い。なお、CaOは、CaCO3、Ca(OH)2等の形態
で、また、MgOは、MgCO3、Mg(OH)2等の形態
で配合することができる。
Further, the transparent neutron shielding glass of the present invention contains CaO and / or MgO as a molding aid. The total content of CaO and MgO is in the range of 1 to 4% by weight. When the blending amount is less than 1% by weight, it is not preferable because the effect of addition does not appear.
If it exceeds, transparency is adversely affected, which is not preferable. Note that CaO can be added in the form of CaCO 3 , Ca (OH) 2, etc., and MgO can be added in the form of MgCO 3 , Mg (OH) 2 .

【0020】なお、上記組成を有する本発明の透明中性
子遮蔽ガラスの製造方法は、特に限定されるものではな
く、慣用の方法を用いて行うことができる。
The method for producing the transparent neutron shielding glass of the present invention having the above composition is not particularly limited, and a conventional method can be used.

【0021】[0021]

【実施例】以下に実施例を挙げて本発明を説明するが、
本発明は以下の実施例に限定されるものではないことを
理解されたい。 実施例 原料としてSiO2:600g、Li2CO3:400
g、B23:100g、Al23:50g、MgCO3
+CaCO3:40gを使用し、上記原料を均質に混合
した後、白金るつぼ内にて1350℃で溶融した。更
に、1350〜1400℃で数時間清澄処理をした後、
約1200℃で20cm×20cm×1cmの型に鋳込
み、室温まで冷却した。次に、500℃で30分間加熱
処理することにより歪みを取り除いた。得られたガラス
板の表面は研磨により平滑にした。得られたガラス板
は、密度2.4g/cm3、熱膨張係数8.5×10-6
℃、屈折率1.48ndを有するものであった。
The present invention will be described below with reference to examples.
It should be understood that the invention is not limited to the examples below. Example SiO 2 as raw material: 600 g, Li 2 CO 3 : 400
g, B 2 O 3 : 100 g, Al 2 O 3 : 50 g, MgCO 3
+ CaCO 3 : 40 g was used, and the above raw materials were homogeneously mixed and then melted at 1350 ° C. in a platinum crucible. Furthermore, after clarification treatment at 1350-1400 ° C. for several hours,
It was cast in a mold of 20 cm × 20 cm × 1 cm at about 1200 ° C. and cooled to room temperature. Next, the strain was removed by heat treatment at 500 ° C. for 30 minutes. The surface of the obtained glass plate was smoothed by polishing. The obtained glass plate had a density of 2.4 g / cm 3 and a coefficient of thermal expansion of 8.5 × 10 −6 /
It had a refractive index of 1.48 nd at ° C.

【0022】なお、実施例で得られたガラス板の組成を
比較品の組成と共に表1に記載する。なお、表1におい
て成形性は目視により観察したもので、○印は良好、×
印は欠点有りを表す。また、透明性も目視により求めた
もので、○印は良好、×印は不透明部分ありを表す。
The compositions of the glass plates obtained in the examples are shown in Table 1 together with the compositions of comparative products. In addition, in Table 1, the moldability was visually observed.
The mark indicates that there is a defect. In addition, the transparency was also determined by visual observation, and the ◯ mark indicates good and the X mark indicates that there is an opaque portion.

【0023】[0023]

【表1】 [Table 1]

【0024】[0024]

【発明の効果】本発明の透明中性子遮蔽ガラスは、熱中
性子遮蔽能及び高速中性子遮蔽能を有するリチウムを安
価な形態で添加しているので、原子力研究施設、同位体
実験室、再処理施設等の放射線遮蔽ガラス窓等のガラス
を大量に使用する用途において適したものである。
EFFECTS OF THE INVENTION The transparent neutron shielding glass of the present invention contains lithium having a thermal neutron shielding ability and a fast neutron shielding ability in an inexpensive form. Therefore, a nuclear research facility, an isotope laboratory, a reprocessing facility, etc. It is suitable for use in a large amount of glass such as a radiation shielding glass window.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 SiO2:55〜70重量%、Al
23:3〜15重量%、Li2O:10〜20重量%、
23:5〜15重量%及びCaO+MgO:1〜4重
量%を含有してなるガラスからなることを特徴とする透
明中性子遮蔽ガラス。
1. SiO 2 : 55-70% by weight, Al
2 O 3 : 3 to 15% by weight, Li 2 O: 10 to 20% by weight,
B 2 O 3: 5~15 wt% and CaO + MgO: transparent neutron shielding glass, characterized in that it consists of glass comprising 1-4 wt%.
JP28333493A 1993-11-12 1993-11-12 Transparent neutron shielding glass Pending JPH07138044A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP28333493A JPH07138044A (en) 1993-11-12 1993-11-12 Transparent neutron shielding glass

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP28333493A JPH07138044A (en) 1993-11-12 1993-11-12 Transparent neutron shielding glass

Publications (1)

Publication Number Publication Date
JPH07138044A true JPH07138044A (en) 1995-05-30

Family

ID=17664133

Family Applications (1)

Application Number Title Priority Date Filing Date
JP28333493A Pending JPH07138044A (en) 1993-11-12 1993-11-12 Transparent neutron shielding glass

Country Status (1)

Country Link
JP (1) JPH07138044A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2007077680A1 (en) * 2005-12-28 2007-07-12 Ohara Inc. Glass composition
CN104017221B (en) * 2014-04-24 2017-01-18 中国人民解放军第二炮兵装备研究院第四研究所 Borate transparent material, preparation method of borate transparent material and neutron radiation protection lens manufactured by virtue of borate transparent material
WO2022145401A1 (en) 2020-12-28 2022-07-07 新日本繊維株式会社 Inorganic composition and fibers and flakes thereof

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2007077680A1 (en) * 2005-12-28 2007-07-12 Ohara Inc. Glass composition
CN104017221B (en) * 2014-04-24 2017-01-18 中国人民解放军第二炮兵装备研究院第四研究所 Borate transparent material, preparation method of borate transparent material and neutron radiation protection lens manufactured by virtue of borate transparent material
WO2022145401A1 (en) 2020-12-28 2022-07-07 新日本繊維株式会社 Inorganic composition and fibers and flakes thereof
KR20230128019A (en) 2020-12-28 2023-09-01 닛폰 파이버 코포레이션 Inorganic compositions and fibers and flakes thereof

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