JPS5888698A - Moldings for sealing spent nuclear fuel rod and its manufacture - Google Patents
Moldings for sealing spent nuclear fuel rod and its manufactureInfo
- Publication number
- JPS5888698A JPS5888698A JP57195399A JP19539982A JPS5888698A JP S5888698 A JPS5888698 A JP S5888698A JP 57195399 A JP57195399 A JP 57195399A JP 19539982 A JP19539982 A JP 19539982A JP S5888698 A JPS5888698 A JP S5888698A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- rods
- anchor plate
- molded
- matrix
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
Landscapes
- Engineering & Computer Science (AREA)
- Environmental & Geological Engineering (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Powder Metallurgy (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
- Piles And Underground Anchors (AREA)
- Press Drives And Press Lines (AREA)
- Sealing Material Composition (AREA)
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】
本発明は、使用ずみ核燃料棒をその1まの形状もしくは
成形した形状で安全に長期間封入するだめの黒鉛及び硫
化ニッケルから成る円筒形もしくは多角形の成形体並び
に該成形体の製法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a cylindrical or polygonal molded body made of graphite and nickel sulfide that safely encapsulates spent nuclear fuel rods in their single or molded form for a long period of time; Concerning a method for manufacturing a molded object.
原子炉からの使用ずみ燃料要素は、一定時間1)燃料要
素を再処理して、燃料物質を燃料要素製造工程に戻しか
つ分裂生成物を分離しかつ最終貯蔵する(高活性廃棄物
)、又は
2)使用ずみ燃料要素を直接的に最終貯蔵するが試みら
れた。いずれの場合にも、1000年以上安全に適当な
地層内に埋込まれねば彦らない高活性廃棄物が生じる。Spent fuel elements from a nuclear reactor are processed for a period of time by either 1) reprocessing the fuel element to return the fuel material to the fuel element manufacturing process and separating the fission products and final storage (highly active waste); or 2) Direct final storage of spent fuel elements has been attempted. In either case, a highly active waste is produced which must be safely buried in a suitable geological formation for 1000 years or more.
この種の使用ずみ燃料要素を安全に長期間封入するため
には、所望の条件、例えば生じ得る圧力及び温度での密
閉又は塩溶液に対する耐食性を良好に満足する多数の類
型の容器が提案された。容器材料としては、大抵金属及
び非金属材料が使用される。In order to safely contain spent fuel elements of this type for long periods of time, a number of types of containers have been proposed which satisfactorily satisfy the desired conditions, such as sealing at possible pressures and temperatures or corrosion resistance against salt solutions. . As container materials, metals and non-metallic materials are mostly used.
黒鉛は優れた耐食性を有しているので、容器に黒鉛から
成る防食層を施すことが提案された(西Fイツ国特許出
願公開第2942092号明細書)。しかし、燃料要素
を収容するために必要な寸法を有する黒鉛成形体は気密
にもまた液密にも製造され得ないので、引続いて・ξイ
ロカーボン又は炭化珪素を有する被覆が施されている。Since graphite has excellent corrosion resistance, it has been proposed to provide a container with an anticorrosion layer made of graphite (Western German Patent Application No. 2942092). However, since graphite compacts with the necessary dimensions for accommodating the fuel elements cannot be manufactured air-tight or liquid-tight, they are subsequently coated with ξ irocarbon or silicon carbide. .
被覆された容器は、燃料要素の充填後回様に被覆された
蓋で気密及び液密に密封されねばならない。この場合、
黒鉛・ξツキンないしは適当な接着剤を使用すべきであ
る。この種の容器構成の著しい欠点は、大きな寸法を有
する容器の製造及び被覆のために必要である技術費用が
法外に高いことである。更に、このような大きな成形体
は所望の品質要求では被覆され得ない。The coated container must be sealed air-tight and liquid-tight with the coated lid after filling with the fuel element. in this case,
Graphite or a suitable adhesive should be used. A significant disadvantage of this type of container design is the prohibitive technical outlay required for manufacturing and coating containers with large dimensions. Moreover, such large moldings cannot be coated with the desired quality requirements.
更に、黒鉛粉末を結合剤と一緒にプレスすることにより
、放射性及び毒性廃棄物を封入するだめの炭素マ) I
Jラックスら成る成形体を製造することも公知である。Furthermore, by pressing graphite powder together with a binder, a carbon matrix for encapsulating radioactive and toxic wastes can be created.
It is also known to produce molded bodies made of J-Lux.
この場合には、結合剤として有利には硫化ニッケルが使
用される(西ドイツ国特許出願公開第2917437号
明細書)。この成形体は極めて密でありかつ特に塩溶液
に対して良好な腐食及び浸出安定性を有する。In this case, nickel sulfide is preferably used as a binder (DE-A-2917437). The molded bodies are very dense and have good corrosion and leaching stability, especially towards salt solutions.
西ドイツ国特許出願公開第2818781号明細書には
、使用ずみ核燃料棒の環境保全貯蔵法が開示されており
、該方法は核燃料棒をわん曲させかつそうして得られた
・ぞケラトを保護容器内に入れることから成る。この場
合には、核燃料棒は有利にはU字形もしくは巻取られた
ロールに成形される。この方法は、容器を必要としてか
つ核燃料棒の外部への熱導出が比較的悪いという欠点を
有する。DE 28 18 781 A1 discloses an environmentally friendly storage method for used nuclear fuel rods, which involves bending the nuclear fuel rods and placing the resulting nuclear fuel rods in a protective container. Consists of putting inside. In this case, the nuclear fuel rod is preferably formed into a U-shape or into a wound roll. This method has the disadvantage of requiring a container and of relatively poor heat extraction to the outside of the nuclear fuel rod.
前成形した核燃料棒をアルミナ及び薄い鋼製ジャケット
と一緒に等圧で圧縮して、永久貯蔵することができるブ
ロックにすることも公知である〔1スゾレツヘザール(
5prechsaai、 )“第113巻(1980年
)、753〜766頁〕。It is also known to press isobarically preformed nuclear fuel rods together with alumina and a thin steel jacket into blocks that can be stored permanently [1.
113 (1980), pp. 753-766].
しかしながら、この場合も熱導出の問題は最適には解決
されていない。更に、機械的保全性も考えられ得るあら
ゆる貯蔵状況のためには十分でない。However, in this case too the problem of heat extraction is not optimally solved. Furthermore, mechanical integrity is also not sufficient for all conceivable storage situations.
従って、本発明の課題は、良好な熱導出を保証し、良好
な腐食及び浸出安定性を有しかつ高い機械的保全を有す
る、使用ずみ核燃料棒をそのままの形状もしくは成形し
た形状で安全に長期間封入するだめの黒鉛及び硫化ニッ
ケルから成る円筒形もしくは多角形の成形体を提供する
ことであった。It is therefore an object of the present invention to safely extend spent nuclear fuel rods in raw or shaped form, which guarantees good heat extraction, has good corrosion and leaching stability and has high mechanical integrity. The object of the present invention is to provide a cylindrical or polygonal molded body made of graphite and nickel sulfide that can be encapsulated for a period of time.
この課題は、本発明により、ヘラ1範囲及び脚範囲にア
ンカー板をかつ核燃料棒不在帯域の内部に成形体の主軸
に対して平行にアンカー板に固定された金属棒を有する
ことにより解決される。This object is solved according to the invention by having an anchor plate in the spatula 1 region and the leg area and a metal rod fastened to the anchor plate parallel to the main axis of the shaped body inside the nuclear fuel rod-free zone. .
アンカー板及び金属棒のためには、あらゆる慣用の材料
を使用することができるが、鋼を使用するのが有利であ
る。For the anchor plate and the metal rod any customary material can be used, but it is advantageous to use steel.
黒鉛/硫化ニッケルマトリックスと棒との間の機械的結
合を改善するだめには、肉眼的に粕な表面を有する金属
棒を使用するのが有利である。In order to improve the mechanical bond between the graphite/nickel sulphide matrix and the rod, it is advantageous to use a metal rod with a macroscopically grainy surface.
また、成形体は硫化ニッケルを主としてNj、3S2の
形で含有するのが有利であることが立証された1、これ
により腐食及び浸出安定性が一層高められる。成形体は
一般にマトリックス材料として黒鉛75重量係及び硫化
ニッケル25〜90重量係、有利にはその内の少なくと
も80係はNi、3S2の形で含有する。It has also proven advantageous for the shaped body to contain nickel sulfide, primarily in the form Nj,3S21, which further increases the corrosion and leaching stability. The shaped bodies generally contain as matrix materials 75 parts by weight of graphite and 25 to 90 parts by weight of nickel sulphide, preferably at least 80 parts of which are in the form of Ni, 3S2.
本発明の成形体は著しく高い機械的保全性を有する、従
って永久貯蔵のために課せられる要求を余すところなく
満足する。The shaped bodies according to the invention have a particularly high mechanical integrity and therefore fully meet the requirements imposed for permanent storage.
本発明の成形体は、本発明方法により、核燃料棒が埋込
まれた、黒鉛、ニッケル及び硫黄から成る混合物を母型
内で100℃よりも高い温度でプレスすることにより、
使用ずみ核燃料棒をそのままの形状もしくは成形した形
状で安全に長時間封入するだめの黒鉛及び硫化ニッケル
から成る円筒形もしくは多角形の成形体を製造する方法
において、母型にまず黒鉛、ニッケル及び硫黄から成る
マトリックス粉末を、次いで金属棒が固定されたアンカ
ー板を、引続き核燃料棒をマ) IJソックス末と一緒
に、更に金属棒が固定されたもう1つのアンカー板をか
つ次いで再度マトリックス粉末を入れかつ圧縮し、その
際に核燃料棒が埋込まれた範囲のマトリックス粉末を前
圧縮しかつ上にも下にも核燃料棒がマトリックス内に存
在しないアンカー板の範囲にのみ金属棒を取付けること
により製造することができる。この場合、プレスは40
0−500℃の温度で実施するのが有利である。The molded body of the present invention is produced by pressing a mixture of graphite, nickel and sulfur in which nuclear fuel rods are embedded in a matrix at a temperature higher than 100°C by the method of the present invention.
In a method for manufacturing a cylindrical or polygonal molded body made of graphite and nickel sulfide that safely encapsulates spent nuclear fuel rods in their original or molded shape for a long time, graphite, nickel, and sulfur are first added to a matrix. Then add the anchor plate with the metal rods fixed thereon, then add the nuclear fuel rods together with the IJ sock powder, add another anchor plate with the metal rods fixed on it, and then add the matrix powder again. At that time, the matrix powder in the area where the nuclear fuel rods are embedded is pre-compressed, and metal rods are attached only to the area of the anchor plate where there are no nuclear fuel rods in the matrix above or below. can do. In this case, the press is 40
It is advantageous to carry out at temperatures of 0-500°C.
この場合、アンカー板の圧入は、金属棒が核燃料棒不在
の中央及び周辺範囲内を圧縮の際に屑入しかつ硬化した
マトリックス内で固定されるように行なう。これにより
特に引張り及び曲げ負荷における成形体の保全性が著し
く高められる、従って核燃料棒を任意の形状(例えば巻
いた、折曲げたもしくはそのままの形状)で封入するこ
とが可能である1、
有利には核燃料棒を円板状のうずまき体に変形させる、
この際には有利には直径≧80間の中心範囲を開ける。In this case, the anchor plate is pressed in in such a way that the metal rod is compressed in the central and peripheral areas where the nuclear fuel rods are absent and is fixed in the hardened matrix. This significantly increases the integrity of the compact, especially under tensile and bending loads, so that it is possible to encapsulate the nuclear fuel rods in any desired shape (e.g. rolled, folded or straight)1, advantageously. transforms a nuclear fuel rod into a disc-shaped spiral body,
In this case, the central region preferably has a diameter of ≧80 mm.
この燃料棒うず寸き体を製造する際には、ピッチを≦6
欄に保つのが有利であることが立証された。When manufacturing this fuel rod spiral body, the pitch should be ≦6.
It has proven advantageous to keep it in the column.
核燃料含有範囲と核燃料不在範囲のマトリックスの圧縮
比は、両者の範囲内の残留変形性が同じ大きさになるよ
うに相互に合わせる。これにより成形体全長に渡って均
一な全体密度を達成することができる。The compression ratios of the matrices of the nuclear fuel-containing range and the nuclear fuel-free range are matched to each other such that the residual deformability within both ranges is of the same magnitude. This makes it possible to achieve a uniform overall density over the entire length of the compact.
本発明方法によれば、多数の核燃料棒の他に、有利に個
々の燃料棒うず捷き体を黒鉛/硫化ニッケルマトリック
ス内に封入することができる。With the method according to the invention, in addition to a large number of nuclear fuel rods, it is also possible to advantageously encapsulate individual fuel rod coils in a graphite/nickel sulphide matrix.
このような円板は、永久貯蔵のために適当な容器に積み
重ね、必要に応じて容易に取出すこともでき又は永久貯
蔵することもできる。取出しやすくするためには、円板
に中央に掴み穴を設けることもできる。Such disks can be stacked in suitable containers for permanent storage and can be easily removed or stored permanently if desired. To facilitate removal, the disc may also have a central gripping hole.
この方法で、触れられない核燃料棒の他に、汚染された
核燃料棒スリーブを封入することもできる。In addition to untouched nuclear fuel rods, contaminated nuclear fuel rod sleeves can also be enclosed in this way.
次に図示の実施例につき本発明の詳細な説明する。The invention will now be described in detail with reference to the illustrated embodiments.
成形体はヘラ12範囲2及び脚範囲3に夫々1つのアン
カー板を有し、該アンカー板に金属棒4が、評言すれば
成形体をプレスする際に核燃料棒5不在であるアンカー
板1の範囲にのみ固定されている。従って、核燃料棒5
は有利には燃料棒不在の中央部7を有する円板状のうず
まき体に成形されており、従って金属棒牛は成形体の外
側範囲の他に中央部にも配置され得る。The molded body has one anchor plate in each of the spatula 12 region 2 and the leg region 3, on which the metal rod 4 is attached, so to speak, when pressing the molded body, the anchor plate 1 in which the nuclear fuel rods 5 are absent. Fixed only in range. Therefore, nuclear fuel rod 5
is preferably shaped as a disc-shaped spiral body with a central part 7 devoid of fuel rods, so that the metal rods can be arranged not only in the outer regions of the molded body but also in the central part.
次に、実施例により本発明の成形体及び本発明の方法を
詳細に説明する。Next, the molded article of the present invention and the method of the present invention will be explained in detail with reference to Examples.
例1
7) IJソックスの出発粉末として、微粉化した天然
黒鉛437重計係、微粉砕した硫黄15重量係及びニッ
ケル金属粉末41.3重量係から成る混合物を乾式混合
によって製造した。核燃料棒は内径8(転)を有しかつ
密度10.49 / c、rdを有する焼結UO2ベレ
ットで被覆されていた。個々の核燃料棒を適当な鋼製管
に挿入しかつ読管を両側で密閉した。一方の端部な緊定
した核燃料棒を、適当な装置を用いて外側の最大ピッチ
≦6rMI及び直径約260叫を有するうず捷き体にま
きつけた。Example 1 7) As a starting powder for IJ socks, a mixture consisting of 437 parts by weight of pulverized natural graphite, 15 parts by weight of finely ground sulfur and 41.3 parts by weight of nickel metal powder was prepared by dry mixing. The nuclear fuel rod had an internal diameter of 8 (turn) and was coated with a sintered UO2 pellet with a density of 10.49/c, rd. The individual nuclear fuel rods were inserted into a suitable steel tube and the reading tube was sealed on both sides. One end of the taut nuclear fuel rod was wrapped using suitable equipment into a swirler having an outer maximum pitch ≦6rMI and a diameter of about 260 mm.
うずまき体を封入するために、直径300wmを有する
鋼製母型にマトリックス粉末から成る層を充填し、該層
を冷間前圧縮し、その上に5本の金属棒を有するアンカ
ー板(外周に3本、内部に2本)を置いた。アンカー板
上に別の厚さ10mmのマトリックス粉末層を施した。In order to encapsulate the spiral body, a steel master mold with a diameter of 300 wm is filled with a layer of matrix powder, which is cold pre-pressed and on which an anchor plate with five metal rods (on the outer periphery) is placed. 3 bottles, 2 bottles inside). Another 10 mm thick layer of matrix powder was applied onto the anchor plate.
その上に核燃料棒うずまき体を置き、次いで7トリソク
ス粉末をほぼ核燃料棒うずまき体の層厚に一致する高さ
に充填した。うずまき体の中央及び周辺範囲で、マトリ
ックス粉末含量を付加的に前圧縮することにより約30
%高めた。成形体を構成するために、更に39個のうず
捷き体を前記工程に基づき層状に積ねて配置した。雇後
のうず捷き体の上端面に、ずらして配置された金属棒を
有する第2のアンカー板を差し込んだ。このアンカー板
の上に、本方法の開始時に下に充填したと同じ量の別の
マトリックス粉末を充填した。130℃に加熱した後、
プレス圧50MN/−で仕上げプレスした。硫黄/ニッ
ケル混合物を反応させてNi、3S2に″変えるために
、圧力を保持した状態で温度を450℃に高めた。A nuclear fuel rod spiral was placed thereon, and then 7 trisox powder was filled to a height approximately corresponding to the layer thickness of the nuclear fuel rod spiral. In the central and peripheral areas of the spiral body, the matrix powder content is reduced by additional precompacting to approximately 30
% increased. In order to construct a molded body, 39 swirl bodies were further stacked and arranged in layers based on the above process. After installation, a second anchor plate having metal rods arranged in a staggered manner was inserted into the upper end surface of the whirlpool body. On top of this anchor plate was filled another matrix powder in the same amount as was filled below at the beginning of the process. After heating to 130℃,
Finish pressing was performed at a pressing pressure of 50 MN/-. To react the sulfur/nickel mixture to Ni, 3S2, the temperature was increased to 450° C. while maintaining pressure.
300℃に冷却した後、成形体を押出した。After cooling to 300°C, the molded body was extruded.
仕上げプレスした成形体は以下の特性を有していた。The finished pressed molded product had the following characteristics.
ψ=300謳
H=760喘
マトリックス密度 3.3 f / cr
ll密度 理論値の97%
熱伝導性 0.8 W/crn、
X線状熱膨張係数 9.2石/ m
、 K耐圧強度 107MN/m
2例2
例1と同様にして、マトリックス粉末を製造した。カプ
セルに充填された長さ約5mの核燃料棒を20回折曲げ
た、従って高さ450m++で幅は250職であった。ψ=300 H=760 Matrix density 3.3 f/cr
ll density 97% of theoretical value Thermal conductivity 0.8 W/crn,
X-ray thermal expansion coefficient 9.2 stones/m
, K pressure resistance 107MN/m
Example 2 A matrix powder was produced in the same manner as in Example 1. The nuclear fuel rods filled in the capsule, about 5 m long, were bent 20 times, so the height was 450 m++ and the width was 250 mm.
折曲げた燃料棒を4角形母型に封入した。第1のマトリ
ックス粉末層を充填しかつ外側に2本の金属棒を有する
アンカー板を入れた後、6個の折曲げた燃料棒を配置し
かつその中空にマトリックス粉末を充填した。ずらして
配置された金属棒を有する第2のアンカー板を入れた後
、その上に本方法の開始時に充填したと同じ量のマトリ
ックス粉末を積層した。プレスは例1と同様にして行な
った。The bent fuel rods were enclosed in a rectangular matrix. After filling the first matrix powder layer and inserting the anchor plate with two metal rods on the outside, six bent fuel rods were placed and the hollows were filled with matrix powder. After introducing the second anchor plate with staggered metal rods, the same amount of matrix powder as filled at the beginning of the method was laminated onto it. Pressing was carried out in the same manner as in Example 1.
仕上げプレスした成形体のマ) IJソックス性は、例
1に記載の成形体の特性に一致した。The IJ sock properties of the finished pressed compacts corresponded to the properties of the compacts described in Example 1.
第1図は本発明の成形体の略示縦断面図、第2図はうず
まき体の形状の核燃料棒を示す図である。
1・・・アンカー板、2・・・ヘッド範囲、3・・・脚
範囲、牛・・・金属棒、5 ・核燃料棒、6・・・うず
まき体、7・・・中央範囲
第1頁の続き
0発 明 者トーマス・シュミット−パンスベルク
ドイツ連邦共和国フランクフル
ト50リンデンリング37
0発 明 者 パンス・フシュカ
ドイツ連邦共和国ハナウ9グリ
ューナウシュトラーセ7
543−FIG. 1 is a schematic longitudinal sectional view of a molded body of the present invention, and FIG. 2 is a diagram showing a spiral-shaped nuclear fuel rod. 1... Anchor plate, 2... Head range, 3... Leg range, Cow... Metal rod, 5 - Nuclear fuel rod, 6... Spiral body, 7... Center range, first page Continued 0 Inventors Thomas Schmidt-Pansberg 50 Lindenring, Federal Republic of Germany 50 Lindenring 37 0 Inventors Pans Huschka 9 Grünaustrasse 7, Hanau, Federal Republic of Germany 543-
Claims (1)
た形状で安全に長期間封入するための黒鉛及び硫化ニッ
ケルから成る円筒形もしくは多角形の成形体において、
ヘラ12範囲(2)及び脚範囲(3)にアンカー板(1
)をかつ核燃料棒不在帯域の内部に成形体の主軸に対し
て平行にアンカー板(1)に固定された金属棒(4)を
有することを特徴とする、使用ずみ核燃料棒を封入する
成形体。 2 金属棒(4)が肉眼的に粗な面を有する、特許請求
の範囲第1項記載の成形体。 3 硫化ニッケルなNi3S2の形で含有する、特許請
求の範囲第1項又は第2項記載の成形体3.4、 核燃
料棒(5)が円板状のうずまき体(6)に成形されてお
り、該うずまき体が直径≧80咽を有する核燃料物質不
在の中央範囲(7)を有している、特許請求の範囲第1
項〜第3項のいずれか1項に記載の成形体。 5 円板状うずまき体(6)のピッチが≦6爺である、
特許請求の範囲第1項〜第4項のいずれか1項に記載の
成形体。 6 核燃料棒(5)の円板状うずまき体(6)のみを特
徴する特許請求の範囲第1項〜第5項のいずれか1項に
記載の成形体。 7、 核燃料棒が埋込捷れた、黒鉛、ニッケル及び硫黄
から成る混合物を母型内で1. O0℃よりも高い温度
でプレスすることにより、使用ずみ核燃料棒をそのまま
の形状もしくは成形した形状で安全に長時間封入するだ
めの黒鉛及び硫化ニッケルから成る円筒形もしくは多角
形の成形体を製造する方法において、母型にまず黒鉛、
ニッケル及び硫黄から成るマトリックス粉末を、次いで
金属棒が固定されたアンカー板を、引続き核燃料棒なマ
) IJソックス末と一緒に、更に金属棒が固定された
もう1つのアンカー板をかつ次いで再度7トリツクス粉
末を入れかつ圧縮し、その際に核燃料棒が埋込まれた範
囲のマトリックス粉末を前圧縮しかつ上にも下にも核燃
料棒がマトリックス内に存在しないアンカー板の範囲に
のみに金属棒を取付けることを特徴とする、使用ずみ核
燃料棒を封入する成形体の製法。 86 仕上げプレスの際に400〜500℃の温度を
特徴する特許請求の範囲第7項記載の方法。[Scope of Claims] (1) A cylindrical or polygonal molded body made of graphite and nickel sulfide for safely enclosing used nuclear fuel rods in a raw or molded shape for a long period of time,
Anchor plate (1) on spatula 12 range (2) and leg range (3)
) and a metal rod (4) fixed to an anchor plate (1) parallel to the main axis of the molded body inside the nuclear fuel rod absent zone, the molded body enclosing a used nuclear fuel rod. . 2. The molded article according to claim 1, wherein the metal rod (4) has a macroscopically rough surface. 3 Molded body 3.4 according to claim 1 or 2 containing nickel sulfide in the form of Ni3S2, in which a nuclear fuel rod (5) is formed into a disc-shaped spiral body (6). , the spiral body has a central region (7) free of nuclear fuel material with a diameter ≧80 mm.
The molded article according to any one of Items 1 to 3. 5 The pitch of the disc-shaped spiral body (6) is ≦6.
The molded article according to any one of claims 1 to 4. 6. The molded article according to any one of claims 1 to 5, characterized only by the disc-shaped spiral body (6) of the nuclear fuel rod (5). 7. A mixture of graphite, nickel and sulfur in which nuclear fuel rods have been embedded is placed in a matrix. By pressing at a temperature higher than 0°C, a cylindrical or polygonal molded body made of graphite and nickel sulfide is produced that can safely encapsulate spent nuclear fuel rods in their original or molded shape for a long time. In the method, graphite is first added to the matrix,
A matrix powder consisting of nickel and sulfur is then added to the anchor plate to which the metal rods are fixed, followed by another anchor plate to which the metal rods are fixed together with the IJ sock powder, and then again to the anchor plate to which the metal rods are fixed. The matrix powder in the area where the nuclear fuel rods are embedded is pre-compressed, and the metal rods are placed only in the area of the anchor plate where there are no nuclear fuel rods in the matrix either above or below. A method for manufacturing a molded body for enclosing used nuclear fuel rods, characterized by attaching a. 86. The method according to claim 7, characterized by a temperature of 400 to 500° C. during finishing pressing.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE31447554 | 1981-11-11 | ||
DE3144755A DE3144755C2 (en) | 1981-11-11 | 1981-11-11 | Shaped body for incorporating spent nuclear fuel rods and process for its manufacture |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS5888698A true JPS5888698A (en) | 1983-05-26 |
Family
ID=6146108
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP57195399A Pending JPS5888698A (en) | 1981-11-11 | 1982-11-09 | Moldings for sealing spent nuclear fuel rod and its manufacture |
Country Status (6)
Country | Link |
---|---|
EP (1) | EP0081660B1 (en) |
JP (1) | JPS5888698A (en) |
BR (1) | BR8206478A (en) |
DE (2) | DE3144755C2 (en) |
ES (2) | ES8402671A1 (en) |
FI (1) | FI74836C (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5521322A (en) * | 1984-08-09 | 1996-05-28 | Casio Computer Co., Ltd. | Tone information processing device for an electronic musical instrument for generating sounds |
Families Citing this family (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3344525A1 (en) * | 1983-12-09 | 1985-06-20 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | METHOD FOR STORING BURNED FUEL ELEMENTS |
DE3532155C1 (en) * | 1985-09-10 | 1987-02-19 | Kernforschungsanlage Juelich | Ultimately disposable bundle and method for producing it |
AT385435B (en) * | 1986-03-07 | 1988-03-25 | Oesterr Forsch Seibersdorf | METHOD AND DEVICE FOR EMBEDDING AND, IF NECESSARY, REACTIVATING, IN PARTICULAR, TOXIC AND / OR RADIOACTIVE SUBSTANCES OR. DISEASE |
DE19700651C1 (en) * | 1997-01-10 | 1998-09-03 | Siemens Ag | Compression of control and absorber elements to be disposed of from light water reactors |
EA021732B1 (en) | 2008-11-10 | 2015-08-31 | Алд Вакуум Текнолоджиз Гмбх | Matrix material composed of graphite and inorganic binders and suitable for final storage of radioactive waste, method for the manufacture thereof, and processing and use thereof |
DE102009044963B4 (en) * | 2008-11-10 | 2011-06-22 | ALD Vacuum Technologies GmbH, 63450 | Graphite matrix blocks with inorganic binder suitable for storage of radioactive waste and method of making the same |
US8502009B2 (en) | 2008-11-26 | 2013-08-06 | Ald Vacuum Technologies Gmbh | Matrix material comprising graphite and an inorganic binder suited for final disposal of radioactive waste, a process for producing the same and its processing and use |
DE102010003289B4 (en) * | 2010-03-25 | 2017-08-24 | Ald Vacuum Technologies Gmbh | Containers for the storage of radioactive waste and process for its production |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2375695A1 (en) * | 1976-12-21 | 1978-07-21 | Asea Ab | PROCESS FOR THE TREATMENT OF RADIOACTIVE WASTE |
SE413712B (en) * | 1977-05-10 | 1980-06-16 | Asea Ab | WANT TO INCLUDE USED NUCLEAR FUEL WASTE IN A SAFETY CONTAINER |
DE2846845A1 (en) * | 1978-10-27 | 1980-05-08 | Battelle Institut E V | Radioactive fission prod. final storage in glass block - poured around metal filler, e.g. wires to prevent cracking on cooling in mould |
DE2917437C2 (en) * | 1979-04-28 | 1983-11-17 | Nukem Gmbh, 6450 Hanau | Procedure for incorporating radioactive and toxic waste |
DE2942092C2 (en) * | 1979-10-18 | 1985-01-17 | Steag Kernenergie Gmbh, 4300 Essen | Final storage containers for radioactive waste, in particular irradiated nuclear reactor fuel elements |
-
1981
- 1981-11-11 DE DE3144755A patent/DE3144755C2/en not_active Expired
-
1982
- 1982-09-29 FI FI823335A patent/FI74836C/en not_active IP Right Cessation
- 1982-10-23 DE DE8282109826T patent/DE3262446D1/en not_active Expired
- 1982-10-23 EP EP82109826A patent/EP0081660B1/en not_active Expired
- 1982-11-09 JP JP57195399A patent/JPS5888698A/en active Pending
- 1982-11-09 BR BR8206478A patent/BR8206478A/en unknown
- 1982-11-10 ES ES517238A patent/ES8402671A1/en not_active Expired
- 1982-11-10 ES ES1982268417U patent/ES268417Y/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5521322A (en) * | 1984-08-09 | 1996-05-28 | Casio Computer Co., Ltd. | Tone information processing device for an electronic musical instrument for generating sounds |
US5717153A (en) * | 1984-08-09 | 1998-02-10 | Casio Computer Co., Ltd. | Tone information processing device for an electronic musical instrument for generating sounds |
US5847302A (en) * | 1984-08-09 | 1998-12-08 | Casio Computer Co., Ltd. | Tone information processing device for an electronic musical instrument for generating sounds |
Also Published As
Publication number | Publication date |
---|---|
ES517238A0 (en) | 1984-02-01 |
FI74836B (en) | 1987-11-30 |
ES8402671A1 (en) | 1984-02-01 |
FI823335A0 (en) | 1982-09-29 |
FI823335L (en) | 1983-05-12 |
FI74836C (en) | 1988-03-10 |
DE3262446D1 (en) | 1985-03-28 |
EP0081660B1 (en) | 1985-02-20 |
BR8206478A (en) | 1983-09-27 |
DE3144755C2 (en) | 1984-06-28 |
ES268417Y (en) | 1983-12-01 |
EP0081660A1 (en) | 1983-06-22 |
ES268417U (en) | 1983-05-16 |
DE3144755A1 (en) | 1983-05-26 |
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