JPS6270799A - Nuclear radiation absorber - Google Patents
Nuclear radiation absorberInfo
- Publication number
- JPS6270799A JPS6270799A JP61162924A JP16292486A JPS6270799A JP S6270799 A JPS6270799 A JP S6270799A JP 61162924 A JP61162924 A JP 61162924A JP 16292486 A JP16292486 A JP 16292486A JP S6270799 A JPS6270799 A JP S6270799A
- Authority
- JP
- Japan
- Prior art keywords
- absorbent material
- aluminum
- material according
- gadolinium
- alloys
- 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/08—Metals; Alloys; Cermets, i.e. sintered mixtures of ceramics and metals
Landscapes
- Engineering & Computer Science (AREA)
- Ceramic Engineering (AREA)
- Metallurgy (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Absorbent Articles And Supports Therefor (AREA)
- Compositions Of Macromolecular Compounds (AREA)
- Manufacture Of Alloys Or Alloy Compounds (AREA)
- Buildings Adapted To Withstand Abnormal External Influences (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
- Materials For Medical Uses (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Abstract
Description
【発明の詳細な説明】 本発明は核放射線吸収材に係る。[Detailed description of the invention] The present invention relates to nuclear radiation absorbing materials.
原子力産業の発達に伴って、有効で強力な放射線吸収材
の配合及び製造のための研究が世界的規模で進められて
いる。この目的を達成するためには、以下の基準に適合
する製造するための材料を使用する必要がある。BACKGROUND OF THE INVENTION With the development of the nuclear power industry, research is being conducted on a worldwide scale to formulate and manufacture effective and powerful radiation absorbing materials. To achieve this objective, it is necessary to use materials for manufacturing that comply with the following criteria:
−特別の核特性、即ち実効捕獲断面積が大きい、二次放
出レベルが低い、放射線に対する経時的安定性がよい等
の特性をもつことが必要である。- It is necessary to have special nuclear properties, such as a large effective capture cross section, low secondary emission levels, and good stability against radiation over time.
−特別な中性子線において、放射線の吸収により発生さ
れる熱効果に耐えるような高溶解点を有することが必要
である。- In particular neutron beams it is necessary to have a high melting point to withstand the thermal effects generated by the absorption of radiation.
−発生された熱の迅速な除去を備えるために、良熱伝導
体でなければならない。- Must be a good thermal conductor in order to provide for rapid removal of the heat generated.
−成形し易い機械的特性をもつことが必要である。- It is necessary to have mechanical properties that make it easy to mold.
−動作媒体又は環境において耐腐食性でなければならな
い。そして
−コストができるだけ低いことが必要である。- Must be corrosion resistant in the operating medium or environment. and - it is necessary that the costs be as low as possible.
中性子吸収に使用される全ての材料のうちで、最も広く
和られているものは力Ｆミウム、サマリウム、ユーロピ
ウム、ホウ素及びガドリニウムである。Of all the materials used for neutron absorption, the most widely used are Fmium, samarium, europium, boron, and gadolinium.
カドミウムの欠点は、毒性が強く、融点が極めて低く（
３２１Ｃ）また沸点も極めて低い（７６５℃）ことであ
る。サマリウムとユーロピウムとは極めてコストが高い
のでその工業利用は実質的に皆無である。The disadvantages of cadmium are that it is highly toxic and has an extremely low melting point (
321C) It also has an extremely low boiling point (765°C). Samarium and europium are extremely expensive, so their industrial use is virtually non-existent.
これら材料のうちで最も普及しているものはホウ素であ
り、種々の形態で使用されており、例えば元素ホウ素、
ホウ化物、炭化ホウ素、ホウ酸等がある。更にこの物質
を対象として多数の特許が出願されている。しかし乍ら
この材料の欠点は機械的特性がよくないことであシ、従
って、各種の吸収材の所望形態の維持に必要な品質を得
るために例えばアルミニウムの如き金属マトリクス中で
高度に希釈する必要がある。しかし乍らこの場合、放射
線吸収能力が極度に低下し、これを補償するためには使
用される材料の量を増加させなければならない。このこ
とは結局、吸収材のコスト増につながる。また、ホウ素
はアルミニウムに実質的に不溶なので、得られる材料が
複合物質であり、その製造にはアルミニウムマトリクス
中にホウ素を均等に分散させ吸収能力にムラが生じない
ようにするには、極めて複雑な製造プロセスが必要であ
る。The most widespread of these materials is boron, which is used in various forms, such as elemental boron,
Examples include borides, boron carbide, and boric acid. Additionally, numerous patents have been filed for this substance. However, the disadvantage of this material is that its mechanical properties are poor, and therefore it must be highly diluted in a metal matrix, e.g. aluminum, to obtain the qualities necessary to maintain the desired morphology of the various absorbents. There is a need. However, in this case the radiation absorption capacity is severely reduced, and to compensate for this the amount of material used must be increased. This ultimately leads to an increase in the cost of the absorbent material. Additionally, since boron is virtually insoluble in aluminum, the resulting material is a composite material, and its manufacture requires extremely complex dispersion of boron evenly within the aluminum matrix to ensure uniform absorption capacity. A manufacturing process is required.
ガドリニウム及びその酸化物は種々の原子力装置で以前
から使用されており、燃料と混合されて減速材の機能を
果たす。しかし乍ら、放射線吸収材の製造に使用するた
めには問題がちる。Gadolinium and its oxides have long been used in various nuclear devices, where they are mixed with fuel to act as a moderator. However, there are problems when using it for manufacturing radiation absorbing materials.
一般的に粉末の形態で得られるガドリニウムの酸化物は
別の物質と混合して使用される必要があり、このために
は極めて複雑な技術を要する。また、機械的特性が極め
てよくないので複雑な形状の吸収材の製造に注意を要し
コストも高い。更に、酸化物の欠点は熱伝導率のレベル
が低いことであり、元素カドＩＪ ニウムに比較して吸
収能力が比較的低い。Gadolinium oxide, which is generally obtained in powder form, must be used in admixture with other substances, which requires extremely complex technology. In addition, since the mechanical properties are extremely poor, care must be taken in manufacturing absorbent materials with complicated shapes, resulting in high costs. Furthermore, the disadvantage of oxides is their low level of thermal conductivity and relatively low absorption capacity compared to elemental cadmium.
ガドリニウムの金属自体に関して考えると、コストがい
っそう高くなり、また極めて酸化し易いので使用が難し
い。Regarding the metal itself, gadolinium is even more expensive and is extremely susceptible to oxidation, making it difficult to use.
しかし乍ら、低速中性子の領斌では、ガドＩＪ ニウム
は公知の全ての吸収材のうちで最大の実効捕獲断面積を
もつ。特にホウ素と比較すると、エネルギレベル１０
ｅＶの熱中性子の断面積は１００倍の大きさである
。高速中性子に関しては、ガドリニウムとホウ素との有
効性は同程度である。However, in the realm of slow neutrons, GadIJnium has the largest effective capture cross section of all known absorbers. Energy level 10, especially when compared to boron
The cross section of eV thermal neutrons is 100 times larger. For fast neutrons, gadolinium and boron are equally effective.
このような理由から、本出願人はガドリニウムの利点と
欠点とを熟知したうえで、ガドリニウムからすぐれた核
放射線吸収材を製造する方法を研究しその開発に成功し
た。For these reasons, the applicant of the present application has studied and succeeded in developing a method for producing an excellent nuclear radiation absorbing material from gadolinium, after being fully aware of the advantages and disadvantages of gadolinium.
吸収材の特徴は、純アルミニウムと合金アルミニウムと
分散相含有の純もしくは合金アルミニウムから成るグル
ープから選択されたアルミニウムとガドリニウムとの合
金から形成されることである。The absorbent material is characterized in that it is formed from an alloy of gadolinium and aluminum selected from the group consisting of pure aluminum, alloyed aluminum, and pure or alloyed aluminum with a dispersed phase.
従って吸収材はガドリニウム０．０５〜７０重量係を含
有するガドリニウム−アルミニウムベースの合金である
。ガドＩＪ ニウム０．０５％未満では吸収効果が過度
に低下し、７０悌を上回ると合金の形成が難しい。上記
範囲は好ましくは０．１〜１５俤であり、吸収すべき放
射線の種類と束とに左右される。The absorbent material is therefore a gadolinium-aluminum based alloy containing 0.05 to 70 gadolinium. Gad IJ If the content is less than 0.05%, the absorption effect will be excessively reduced, and if it exceeds 70%, it will be difficult to form an alloy. The range is preferably from 0.1 to 15 degrees and depends on the type and flux of radiation to be absorbed.
使用される純アルミニウムは、３層電解もしくは分別晶
出の如き任意の方法で精製されたものでもよく、又は鉄
及びケイ素の如き通常の不純物と共に電解槽の出口で収
集された−１１でもよい。The pure aluminum used may be purified by any method such as three-layer electrolysis or fractional crystallization, or it may be -11 collected at the outlet of the electrolytic cell along with the usual impurities such as iron and silicon.
または、アルミニウムがアルミニウム協会規格の表示番
号１０００．５０００及び６０００の従来の合金でもよ
い。これら合金は、製造される吸収材の機械的特性を強
化し得る。または、カドミウム、サマリウム、ユーロピ
ウム、リチウム、ハフニウム及びタンタルの如き同じく
吸収質の別の１種類以上の金属とアルミニウムとの合金
を使用してもよい。これら合金はタイプ１０００．５０
００及び６０００の合金から製造され得る。Alternatively, the aluminum may be conventional alloys with Aluminum Institute designation numbers 1000, 5000 and 6000. These alloys can enhance the mechanical properties of the absorbent material produced. Alternatively, alloys of aluminum with one or more other metals that are also absorbing, such as cadmium, samarium, europium, lithium, hafnium, and tantalum, may be used. These alloys are type 1000.50
00 and 6000 alloys.
更に、合金又は合金でないアルミニウムが、吸収材の機
械的強度を改良するだめの炭素繊維もしくはその他の繊
維の如き分散相を含んでいてもよい。また、かかる繊維
と任意に組合せて放射線吸収物質例えばホウ素及びその
誘導体を使用アルミニウムの３０重量％未満までの量で
含んでいてもよい。Additionally, the alloyed or unalloyed aluminum may contain a dispersed phase such as carbon fibers or other fibers to improve the mechanical strength of the absorbent material. It may also contain, optionally in combination with such fibers, radiation absorbing substances such as boron and its derivatives in amounts up to less than 30% by weight of the aluminum used.
本発明方法で製造されるガドＩＪ ニウム−アルミニウ
ム合金は機械的特性がよいので、低圧もしくは高圧の砂
型鋳造もしくはチル鋳造、熱間圧延もしくは冷間圧延、
押出及び鍛造から選択された製法を少なくとも１つ用い
てｆｆ：意の形状の吸収材に容易に成形される。Since the Gad IJ Ni-Al alloy produced by the method of the present invention has good mechanical properties, it can be processed by low-pressure or high-pressure sand casting or chill casting, hot rolling or cold rolling.
Using at least one manufacturing method selected from extrusion and forging, the absorbent material can be easily formed into a desired shape.
かかる合金は、完全に均質な組織をもち極めて均一な実
効捕獲断面積をもつ。更に、Ｑｄの割合次第で比重を変
えることができるので、Ｑｄの割合を３０重量％未′ｔ
ｉ１こするとアルミニウムＩＣ極めて近い比重にするこ
とができ、極めて軽量な中性子バリヤーが得られる。Such alloys have a completely homogeneous structure and a highly uniform effective capture cross section. Furthermore, the specific gravity can be changed depending on the proportion of Qd, so the proportion of Qd can be adjusted to less than 30% by weight.
By rubbing i1, the specific gravity can be made very similar to that of aluminum IC, and an extremely lightweight neutron barrier can be obtained.
以下の表ＩはＱｄの含量が夫々１１％及び２３％の２種
類の二元合金υ−Ｑｄの比重を示す。Table I below shows the specific gravity of two binary alloys υ-Qd with Qd contents of 11% and 23%, respectively.
表Ｉ：二元合金后−Ｑｄの比重
Ｑｄの重量％ 比重
１１ ２．９２
２５ ３．１２
アルミニウムマトリクスは最終製品に好レベルて生じた
熱が外部冷却系に速やかに除去される。Table I: Weight % of Specific Gravity Qd of Binary Alloy After-Qd Specific Gravity 11 2.92 25 3.12 The aluminum matrix provides a good level for the final product and the heat generated is quickly removed to the external cooling system.
合金Ａ／ −Ｇｄの溶融開始温度は極めて高く、多くの
場合６２０Ｃよシ高温である。この特性のため、中性子
又はその他の光線の吸収によって生じた加熱効果ｌこ容
易に耐える中性子バリヤーが形成されるＯ
Ｇｄの原子買値は極めて高＜ （１５６，９ｇ ）、特
にγ線とＸ線とはかな夛の程度まで吸収される。The melting start temperature of alloy A/-Gd is extremely high, often as high as 620C. Because of this property, a neutron barrier is formed that easily withstands the heating effects caused by the absorption of neutrons or other radiation. Absorbed to a fleeting degree.
一般的に耐食性はガドリニウムの存在によって全く又は
殆んど影響を受けない。従って、耐食性は使用アルミニ
ウムマトリクスに極めて近い。シリーズ１０００．５０
００及び６０００の合金は、大気の物質又は海岸の空気
に対してすぐれた耐食性をもつ。この耐食性は更に、適
当な表面処理（陽極酸化、中和（ａｌｏｄｉｎｅ ）、
塗装、プラスチック被膜等）によって強化され得る。Corrosion resistance is generally not or only slightly affected by the presence of gadolinium. Therefore, the corrosion resistance is very close to the aluminum matrix used. Series 1000.50
The 00 and 6000 alloys have excellent corrosion resistance to atmospheric agents or coastal air. This corrosion resistance can be further improved by appropriate surface treatments (anodizing, alodine,
(painting, plastic coating, etc.).
機械的特性は良好であり選択されたアルミニウムマトリ
クスに依存する。アルミニウムーガドリニウムニ元合金
の場合、機械的特性はガドリニウムの活に伴って変化す
る。以下の表■け、Ｇｄを夫々、１２重量及び２５重量
％含む２種類の鋳造合金について得られた結果を示す。The mechanical properties are good and depend on the selected aluminum matrix. In the case of aluminum-gadolinium binary alloys, the mechanical properties change with the activation of gadolinium. The table below shows the results obtained for two cast alloys containing 12 and 25% by weight of Gd, respectively.
表■−υ−Ｑｄ二元合金の機械的特性
以下の表ＩはＱｄを１１重量％含む圧延合金で得られた
結果を示す。Table 1 - Mechanical Properties of Qd Binary Alloys Table I below shows the results obtained with rolled alloys containing 11% by weight of Qd.
銅、ケイ素、亜鉛、マグネシウム等の元素をドープした
アルミニウムマトリクスを使用すると、強度レベルと弾
性限度とが顕著に増加して以下の値に到達し得る。Using an aluminum matrix doped with elements such as copper, silicon, zinc, magnesium, etc., the strength level and elastic limit can be significantly increased to reach the following values:
Ｔ（、ｍ ２８０〜３２０ＭＰＡＲｐ０．
２ ２２０〜２６０ＭＰＡＡチ ３
〜１０優
上記の高いほうの数値は上限値ではなく、三元合金、四
元合金、三元合金等のガドＩＪ ニウム含有合金は上記
の値よシも高い値を与え得る。T(, m 280-320MPARp0.
2 220~260MPAAchi 3
The higher values above ~10 are not upper limits; GadIJ nium-containing alloys such as ternary alloys, quaternary alloys, and ternary alloys can give values even higher than the above values.
これら金属合金の機械加工には全く問題がない。There are no problems in machining these metal alloys.
省１ハすべき）髪うメータ及び処理速度は、アルミニウ
ム合金一般の場合と同じである。The hair meter and processing speed are the same as for aluminum alloys in general.
本発明は、軍事利用又は平和利用に隅わり４．＋１４
（放射線（中性子、γ線、Ｘ線）の吸収が問題となる分
野に多くの用途をもつ。4. The present invention has military or peaceful uses. +14
(It has many applications in fields where absorption of radiation (neutrons, gamma rays, X-rays) is a problem.
本発明の用途として例えば、核廃棄物の輸送及び貯稜用
フラスコ、原子炉燃料要素貯蔵用スイミングプールラッ
ク、除染装置の遮蔽、軍用自動車の遮蔽又は装甲、放射
性降下物シェルタ−１原子炉要素、放射線又は放射能諒
を使用する装置のモニタ用遮Ｍ：等がある。勿論これら
は非限定例である。Applications of the invention include, for example, flasks for the transportation and storage of nuclear waste, swimming pool racks for the storage of nuclear reactor fuel elements, shielding of decontamination equipment, shielding or armoring of military vehicles, fallout shelters - 1 nuclear reactor elements. , shielding M for monitoring equipment that uses radiation or radioactivity. Of course, these are non-limiting examples.
Claims (11)
む純もしくは合金アルミニウムとから成るグループから
選択されたアルミニウムとガドリニウムとの合金によつ
て形成されることを特徴とする核放射線吸収材。(1) A nuclear radiation absorbing material characterized in that it is formed of an alloy of gadolinium and aluminum selected from the group consisting of pure aluminum, alloyed aluminum, and pure or alloyed aluminum containing a dispersed phase.
ることを特徴とする特許請求の範囲第１項に記載の吸収
材。(2) The absorbent material according to claim 1, wherein the proportion of gadolinium is 0.05 to 70% by weight.
ことを特徴とする特許請求の範囲第２項に記載の吸収材
。(3) The absorbent material according to claim 2, wherein the proportion of gadolinium is 0.1 to 15% by weight.
示番号１０００、５０００及び６０００の合金から選択
されることを特徴とする特許請求の範囲第１項に記載の
吸収材。(4) The absorbent material according to claim 1, wherein the aluminum alloy is selected from alloys having designation numbers 1000, 5000, and 6000 of the Aluminum Association standard.
属を含有することを特徴とする特許請求の範囲第１項に
記載の吸収材。(5) The absorbent material according to claim 1, wherein the aluminum alloy contains one or more nuclear radiation absorbing metals.
、リチウム、ハフニウム及びタンタルから成るグループ
に属することを特徴とする特許請求の範囲第５項に記載
の吸収材。(6) Absorbent material according to claim 5, characterized in that the metal belongs to the group consisting of cadmium, samarium, europium, lithium, hafnium and tantalum.
ることを特徴とする特許請求の範囲第１項に記載の吸収
材。(7) The absorbent material according to claim 1, wherein the dispersed phase contains one or more nuclear radiation absorbing substances.
成されることを特徴とする特許請求の範囲第７項に記載
の吸収材。(8) Absorbent material according to claim 7, characterized in that the dispersed phase is formed by boron or one of its derivatives.
を特徴とする特許請求の範囲第８項に記載の吸収材。(9) Absorbent material according to claim 8, characterized in that the boron content is up to 30% by weight of the aluminum.
求の範囲第１項に記載の吸収材。(10) The absorbent material according to claim 1, wherein the dispersed phase is fibrous.
方法を１種類以上用いて製造されることを特徴とする特
許請求の範囲第１項に記載の吸収材。(11) The absorbent material according to claim 1, which is manufactured using one or more manufacturing methods selected from casting, rolling, extrusion, and forging.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR8510983 | 1985-07-11 | ||
| FR8510983A FR2584852B1 (en) | 1985-07-11 | 1985-07-11 | NUCLEAR RADIATION ABSORBER |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6270799A true JPS6270799A (en) | 1987-04-01 |
Family
ID=9321402
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61162924A Pending JPS6270799A (en) | 1985-07-11 | 1986-07-10 | Nuclear radiation absorber |
Country Status (19)
| Country | Link |
|---|---|
| EP (1) | EP0211779B1 (en) |
| JP (1) | JPS6270799A (en) |
| KR (1) | KR910007461B1 (en) |
| AT (1) | ATE40763T1 (en) |
| AU (1) | AU580177B2 (en) |
| BR (1) | BR8603239A (en) |
| CA (1) | CA1268031A (en) |
| DE (1) | DE3662078D1 (en) |
| DK (1) | DK327786A (en) |
| ES (1) | ES2001015A6 (en) |
| FI (1) | FI85923C (en) |
| FR (1) | FR2584852B1 (en) |
| GR (1) | GR861792B (en) |
| IE (1) | IE58952B1 (en) |
| IL (1) | IL79385A0 (en) |
| NO (1) | NO169035C (en) |
| NZ (1) | NZ216802A (en) |
| PT (1) | PT82958B (en) |
| ZA (1) | ZA865168B (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6338553A (en) * | 1986-08-01 | 1988-02-19 | Kobe Steel Ltd | Aluminum alloy having superior thermal neutron absorbing power |
| US7177384B2 (en) | 1999-09-09 | 2007-02-13 | Mitsubishi Heavy Industries, Ltd. | Aluminum composite material, manufacturing method therefor, and basket and cask using the same |
| JP2007533851A (en) * | 2004-04-22 | 2007-11-22 | アルキャン・インターナショナル・リミテッド | Improved neutron absorption efficiency of boron-containing aluminum materials |
| WO2017209038A1 (en) * | 2016-05-30 | 2017-12-07 | 株式会社フジクラ | Gadolinium wire material, method for manufacturing same, metal-coated gadolinium wire material using same, heat exchanger, and magnetic refrigeration device |
| CN108026613A (en) * | 2016-05-30 | 2018-05-11 | 株式会社藤仓 | Gadolinium wire rod and its manufacture method, metal covering gadolinium wire rod, heat exchanger and magnetic refrigeration apparatus using gadolinium wire rod |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE19706758A1 (en) * | 1997-02-20 | 1998-05-07 | Siemens Ag | Apparatus used to store spent fuel elements from nuclear power stations |
| CA2912021C (en) | 2013-06-19 | 2020-05-05 | Rio Tinto Alcan International Limited | Aluminum alloy composition with improved elevated temperature mechanical properties |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5484200A (en) * | 1977-12-16 | 1979-07-04 | Tokushiyu Muki Zairiyou Kenkiy | Neutron absorbent and its preparation |
| JPS6212895A (en) * | 1985-07-10 | 1987-01-21 | 株式会社神戸製鋼所 | Aluminum alloy having excellent neutron absorptivity |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3024892A1 (en) * | 1979-08-18 | 1982-02-11 | Thyssen Industrie Ag, 4300 Essen | Steel castings which can be hardened and tempered - contain lanthanide so they can be used as neutron absorbing shields |
| JPS6055460B2 (en) * | 1980-08-12 | 1985-12-05 | 東芝セラミツクス株式会社 | Alumina sintered pellets for neutron absorption |
| CA1183613A (en) * | 1980-12-27 | 1985-03-05 | Koichiro Inomata | Neutron absorber, neutron absorber assembly utilizing the same, and other uses thereof |
| FR2533943B1 (en) * | 1982-10-05 | 1987-04-30 | Montupet Fonderies | PROCESS FOR THE MANUFACTURE OF COMPOSITE ALLOYS BASED ON ALUMINUM AND BORON AND ITS APPLICATION |
| DE3335888A1 (en) * | 1983-10-03 | 1985-04-18 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | METHOD FOR REDUCING THE REACTIVITY OF A GAS-COOLED BULLET HEAD REACTOR AND SHUT-OFF ELEMENT |
-
1985
- 1985-07-11 FR FR8510983A patent/FR2584852B1/en not_active Expired
-
1986
- 1986-07-09 AT AT86420187T patent/ATE40763T1/en not_active IP Right Cessation
- 1986-07-09 EP EP86420187A patent/EP0211779B1/en not_active Expired
- 1986-07-09 NZ NZ216802A patent/NZ216802A/en unknown
- 1986-07-09 DE DE8686420187T patent/DE3662078D1/en not_active Expired
- 1986-07-09 GR GR861792A patent/GR861792B/en unknown
- 1986-07-10 PT PT82958A patent/PT82958B/en not_active IP Right Cessation
- 1986-07-10 IL IL79385A patent/IL79385A0/en not_active IP Right Cessation
- 1986-07-10 BR BR8603239A patent/BR8603239A/en unknown
- 1986-07-10 ES ES8600232A patent/ES2001015A6/en not_active Expired
- 1986-07-10 IE IE185186A patent/IE58952B1/en not_active IP Right Cessation
- 1986-07-10 AU AU60048/86A patent/AU580177B2/en not_active Ceased
- 1986-07-10 CA CA000513519A patent/CA1268031A/en not_active Expired - Fee Related
- 1986-07-10 DK DK327786A patent/DK327786A/en not_active Application Discontinuation
- 1986-07-10 JP JP61162924A patent/JPS6270799A/en active Pending
- 1986-07-10 ZA ZA865168A patent/ZA865168B/en unknown
- 1986-07-10 KR KR1019860005558A patent/KR910007461B1/en not_active IP Right Cessation
- 1986-07-10 FI FI862902A patent/FI85923C/en not_active IP Right Cessation
- 1986-07-10 NO NO862793A patent/NO169035C/en unknown
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5484200A (en) * | 1977-12-16 | 1979-07-04 | Tokushiyu Muki Zairiyou Kenkiy | Neutron absorbent and its preparation |
| JPS6212895A (en) * | 1985-07-10 | 1987-01-21 | 株式会社神戸製鋼所 | Aluminum alloy having excellent neutron absorptivity |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6338553A (en) * | 1986-08-01 | 1988-02-19 | Kobe Steel Ltd | Aluminum alloy having superior thermal neutron absorbing power |
| US7177384B2 (en) | 1999-09-09 | 2007-02-13 | Mitsubishi Heavy Industries, Ltd. | Aluminum composite material, manufacturing method therefor, and basket and cask using the same |
| JP2007533851A (en) * | 2004-04-22 | 2007-11-22 | アルキャン・インターナショナル・リミテッド | Improved neutron absorption efficiency of boron-containing aluminum materials |
| WO2017209038A1 (en) * | 2016-05-30 | 2017-12-07 | 株式会社フジクラ | Gadolinium wire material, method for manufacturing same, metal-coated gadolinium wire material using same, heat exchanger, and magnetic refrigeration device |
| CN108026613A (en) * | 2016-05-30 | 2018-05-11 | 株式会社藤仓 | Gadolinium wire rod and its manufacture method, metal covering gadolinium wire rod, heat exchanger and magnetic refrigeration apparatus using gadolinium wire rod |
Also Published As
| Publication number | Publication date |
|---|---|
| PT82958B (en) | 1993-03-31 |
| EP0211779B1 (en) | 1989-02-08 |
| NO862793D0 (en) | 1986-07-10 |
| KR870001611A (en) | 1987-03-14 |
| GR861792B (en) | 1986-11-04 |
| DK327786A (en) | 1987-01-12 |
| PT82958A (en) | 1986-08-01 |
| ES2001015A6 (en) | 1988-04-16 |
| FI85923C (en) | 1992-06-10 |
| FR2584852B1 (en) | 1987-10-16 |
| AU6004886A (en) | 1987-01-15 |
| ATE40763T1 (en) | 1989-02-15 |
| BR8603239A (en) | 1987-02-24 |
| FR2584852A1 (en) | 1987-01-16 |
| NO169035C (en) | 1992-04-29 |
| DK327786D0 (en) | 1986-07-10 |
| KR910007461B1 (en) | 1991-09-26 |
| FI85923B (en) | 1992-02-28 |
| EP0211779A1 (en) | 1987-02-25 |
| IE58952B1 (en) | 1993-12-01 |
| IE861851L (en) | 1987-01-11 |
| NO169035B (en) | 1992-01-20 |
| IL79385A0 (en) | 1986-10-31 |
| NO862793L (en) | 1987-01-12 |
| DE3662078D1 (en) | 1989-03-16 |
| FI862902A0 (en) | 1986-07-10 |
| NZ216802A (en) | 1989-06-28 |
| AU580177B2 (en) | 1989-01-05 |
| ZA865168B (en) | 1987-03-25 |
| FI862902A (en) | 1987-01-12 |
| CA1268031A (en) | 1990-04-24 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US2727996A (en) | Thermal neutron shield and method for making same | |
| US2805473A (en) | Uranium-oxide-containing fuel element composition and method of making same | |
| Jing et al. | Research progress of rare earth composite shielding materials | |
| EP0225226B1 (en) | Aluminum alloy with superior thermal neutron absorptivity | |
| Gan et al. | Research progress of metal-based shielding materials for neutron and gamma rays | |
| CN110643859A (en) | Aluminum-based composite material containing gadolinium-tungsten element and application thereof | |
| JPS6270799A (en) | Nuclear radiation absorber | |
| Van Houten | Selected engineering and fabrication aspects of nuclear metal hydrides (Li, Ti, Zr, and Y) | |
| CN118186256A (en) | Aluminum gadolinium alloy material for nuclear shielding, preparation method and application thereof | |
| CH667880A5 (en) | NUCLEAR RADIATION ABSORBER. | |
| CN109763022A (en) | A kind of nuclear reactor 150-250 degree is radiated metals with having double fusing points | |
| US2871176A (en) | Nuclear reactor component cladding material | |
| JP3128620B2 (en) | Neutron absorbing alloy | |
| CN104611653B (en) | Al B are used in a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials | |
| Kamada et al. | Development of low activation Al alloys for DT burning fusion device | |
| JPS6338553A (en) | Aluminum alloy having superior thermal neutron absorbing power | |
| Greenspan et al. | Blanket energy multiplication enhancement without afterheat safety hazards | |
| US3188202A (en) | Aluminum-plutonium alloys | |
| KR20240011625A (en) | Chemical compositions of Ti-Gd based alloys with improved neutron absorbing capability and tensile properties, and neutron absorbing structural materials manufactured through the same | |
| US3928027A (en) | Nonswelling alloy | |
| US3198629A (en) | Uranium-vanadium-aluminum ternary alloy | |
| US3112196A (en) | Metal alloy suitable for controlling thermal neutron reactors | |
| JPS6126738A (en) | Zirconium alloy | |
| CN109797312A (en) | A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal | |
| Horak et al. | The Effects of Irradiation on some Binary Alloys of Thorium-Plutonium and Zirconium-Plutonium |