JP2655908B2 - Method for producing nuclear fuel pellet containing gatolinium oxide having large crystal grain size - Google Patents
Method for producing nuclear fuel pellet containing gatolinium oxide having large crystal grain sizeInfo
- Publication number
- JP2655908B2 JP2655908B2 JP1058421A JP5842189A JP2655908B2 JP 2655908 B2 JP2655908 B2 JP 2655908B2 JP 1058421 A JP1058421 A JP 1058421A JP 5842189 A JP5842189 A JP 5842189A JP 2655908 B2 JP2655908 B2 JP 2655908B2
- Authority
- JP
- Japan
- Prior art keywords
- oxide
- nuclear fuel
- grain size
- crystal grain
- aluminum
- 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
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Inorganic Compounds Of Heavy Metals (AREA)
- Compositions Of Oxide Ceramics (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 この発明は、大結晶粒径を有する酸化ガドリニウム入
り二酸化ウラン核燃料ペレットの製造方法に関するもの
である。Description: TECHNICAL FIELD The present invention relates to a method for producing gadolinium oxide-containing uranium dioxide nuclear fuel pellets having a large crystal grain size.
従来、原子燃料としては、二酸化ウランの焼結ペレッ
トをジルカロイ等の被覆管に充填したものが原子燃料要
素として使用されていた。Conventionally, as a nuclear fuel, a uranium dioxide sintered pellet filled in a cladding tube made of Zircaloy or the like has been used as a nuclear fuel element.
ところが、最近、酸化ガドリニウム入り二酸化ウラン
の焼結ペレットをラジカロイ等の被覆管に充填したもの
が原子燃料要素として使用されはじめている。上記酸化
ガドリニウム入り二酸化ウランの焼結ペレットを充填し
た原子燃料要素は、その中に中性子吸収能力を有するガ
ドリニウムを含むために、原子燃料要素そのものがバー
ナブルポイズン棒（Burnable Poison Rod、以下BP棒と
いう）と同様に炉心反応度を抑制する役割を果す。これ
は現在の原子力プラントの稼動率を向上させるために、
さらにウランの濃縮度を上げて長サイクル運転をしよう
とする場合に必要となる炉心寿命初期の余剰反応度の抑
制および減速材温度係数を十分負側に保つのを、BP棒の
数を増やすことなく上記酸化ガドリニウム入り二酸化ウ
ランの焼結ペレットを充填した原子燃料要素を使用する
ことで解決でき、原子炉を用いた原子力発電の経済性を
大いに高めるものである。However, recently, gadolinium oxide-containing uranium dioxide sintered pellets filled in a cladding tube of radiocaloy or the like have begun to be used as nuclear fuel elements. Since the nuclear fuel element filled with the gadolinium oxide-containing uranium dioxide sintered pellet contains gadolinium having a neutron absorbing ability, the nuclear fuel element itself is a burnable poison rod (hereinafter referred to as a BP rod). ) Plays the role of suppressing core reactivity. This is to increase the availability of current nuclear plants,
Increasing the uranium enrichment and controlling the excess reactivity in the early life of the core and maintaining the moderator temperature coefficient on the negative side are necessary to increase the number of BP rods. Instead, the problem can be solved by using a nuclear fuel element filled with sintered pellets of gadolinium oxide-containing uranium dioxide, thereby greatly improving the economics of nuclear power generation using a nuclear reactor.
上記酸化ガドリニウム入り二酸化ウラン焼結ペレット
は、通常の二酸化ウラン粉末に３〜15重量％の酸化ガド
リニウムを配合し、これに潤滑剤を加えて混合し、圧粉
体に成形したのち、温度:1700〜1800℃の還元性雰囲気
中で焼結することにより製造される。The above uranium dioxide sintered pellet containing gadolinium oxide is prepared by mixing 3 to 15% by weight of gadolinium oxide with ordinary uranium dioxide powder, adding a lubricant thereto, mixing the mixture, and forming a green compact. It is manufactured by sintering in a reducing atmosphere at 11800 ° C.
上記酸化ガドリニウム入り二酸化ウラン焼結ペレット
をジルカロイ等の被覆管に充填してなる原子燃料要素
は、核***を行なうと、核***によってキセノン、クリ
プトン等の核***生成ガス（Fission Product Gas,以
下、FPガスという）が発生し、かかるFPガスが被覆管内
部に発生すると、高いガス圧が生じ、被覆管が破損する
危険が生じるという問題点があった。When nuclear fission is performed, the nuclear fuel element obtained by filling gadolinium oxide-containing uranium dioxide sintered pellets in a cladding tube such as zircaloy is a fission product gas (hereinafter referred to as FP gas) such as xenon or krypton. ) Occurs, and when such FP gas is generated inside the cladding tube, a high gas pressure is generated, and there is a problem that the cladding tube may be damaged.
このため、核燃料ペレットから発生する上記FPガス放
出抑制のための手段の１つとして、二酸化ウラン単体か
らなるペレットについては、その圧粉体の焼結中に結晶
粒を成長させ、FPガス保有能力を焼結体ペレットに付与
する方法が提案されているが、酸化ガドリニウム入り酸
化ウラン核燃料ペレットについては、いまだ解決されて
いないのが現状である。Therefore, as one of the means for suppressing the release of FP gas generated from nuclear fuel pellets, in the case of pellets made of uranium dioxide alone, crystal grains grow during sintering of the green compact, and the FP gas holding capacity is increased. Has been proposed for imparting gallium oxide to sintered compact pellets, but the present situation has not been solved for uranium oxide nuclear fuel pellets containing gadolinium oxide.
そこで、本発明者等は、FPガス保有能力を有する大結
晶粒径の酸化ガドリニウム入り酸化ウラン核燃料ペレッ
トの製造方法を開発すべく研究を行ったところ、 酸化ガドリニウム粉末を配合した二酸化ウラン粉末
に、さらにアルミニウム化合物をアルミニウムに換算し
て1000〜5000ppm添加することによって結晶粒の大きな
酸化ガドリニウム入り酸化ウラン核燃料ペレットを製造
することができるという知見を得たのである。Therefore, the present inventors conducted research to develop a method for producing gadolinium oxide-containing uranium oxide nuclear fuel pellets having a large crystal grain size having FP gas holding capacity, and found that uranium dioxide powder containing gadolinium oxide powder was Furthermore, it has been found that by adding 1000 to 5000 ppm of an aluminum compound in terms of aluminum, uranium oxide nuclear fuel pellets containing gadolinium oxide with large crystal grains can be produced.
この発明は、かかる知見にもとづいてなされたもので
あって、 平均粒径:8〜10μｍの酸化ガドリニウム粉末:3〜15重
量％を配合した二酸化ウラン粉末に、アルミニウム化合
物をアルミニウムに換算して1000〜5000ppm（0.1〜0.5
重量％）添加し、混合し、この混合粉末をプレス成形し
て圧粉体を作製し、ついでこの圧粉体を焼結することに
より、大結晶粒径を有する酸化ガドリニウム入り二酸化
ウラン核燃料ペレットの製造方法に特徴を有するもので
ある。The present invention has been made on the basis of such findings, and it has been found that gadolinium oxide powder having an average particle size of 8 to 10 μm: ~ 5000ppm (0.1 ~ 0.5
% By weight), mixed, and press-molded the mixed powder to produce a green compact. Then, the green compact was sintered to obtain a gadolinium oxide-containing uranium dioxide nuclear fuel pellet having a large crystal grain size. It is characterized by the manufacturing method.
上記アルミニウム化合物とは、酸化アルミニウム、水
酸化アルミニウム、脂肪酸のアルミニウム塩のうち１種
または２種以上であり、上記脂肪酸のアルミニウム塩と
は、例えばステアリン酸アルミニウム、オレイン酸アル
ミニウム、パルミチン酸アルミニウムなどがあげられる
が、これに限定されるものではない。The aluminum compound is one or more of aluminum oxide, aluminum hydroxide, and an aluminum salt of a fatty acid. Examples of the aluminum salt of the fatty acid include aluminum stearate, aluminum oleate, and aluminum palmitate. But not limited thereto.
Gd2O3粉末入りUO2粉末の圧粉体を作製するために、潤
滑剤として一般にステアリン酸亜鉛が用いられていた
が、上記脂肪酸のアルミニウム塩は圧粉体成形時の潤滑
剤としての機能を有するために、上記ステアリン酸亜鉛
の代用として用いることができ、さらにステアリン酸亜
鉛とともに添加してステアリン酸亜鉛の添加量を減らす
こともできる。Zinc stearate was generally used as a lubricant to produce a green compact of UO 2 powder containing Gd 2 O 3 powder, but the aluminum salt of the above fatty acid functions as a lubricant during green compact molding. Therefore, it can be used as a substitute for the zinc stearate, and can be added together with zinc stearate to reduce the amount of zinc stearate added.
この発明では、主としてGd2O3入り二酸化ウランにつ
いて述べたが、ウランとプルトニウムの混合酸化物でMO
XとよばれるものにGd2O3粉末を添加した核燃料に対して
も同様の効果を有することは理論的に当業者によって認
められよう。In the present invention, uranium dioxide containing Gd 2 O 3 was mainly described, but a mixed oxide of uranium and plutonium was used for MO.
It will be theoretically recognized by those skilled in the art that a similar effect is obtained for a nuclear fuel obtained by adding Gd 2 O 3 powder to what is called X.
つぎに、この発明を実施例にもとづいて具体的に説明
する。Next, the present invention will be specifically described based on embodiments.
平均粒径:0.97μｍのUO2粉末、 平均粒径:5.00μｍのGd2O3粉末、 平均粒径:0.50μｍのAl2O3粉末、 を用意し、第１表の実施例１〜２および比較例１に示さ
れる組成となるように配合し、混合し、混合して得られ
た混合粉末をそれぞれ金型に充填し、3ton/cm2の圧力で
プレス成形して直径:10mm×高さ:15mmの圧粉体を作製し
た。Average particle size: 0.97 μm UO 2 powder, average particle size: 5.00 μm Gd 2 O 3 powder, average particle size: 0.50 μm Al 2 O 3 powder were prepared. Each of the mixed powders obtained by blending and mixing to have the composition shown in Comparative Example 1 was filled in a mold, and press-molded at a pressure of 3 ton / cm 2 to obtain a diameter of 10 mm × high. A compact having a thickness of 15 mm was produced.
これら圧粉体を水素気流中、温度:1750℃で５時間保
持の条件で焼結し、得られたGd2O3入りUO2ペレットを製
造した。 These green compacts were sintered in a hydrogen stream at a temperature of 1750 ° C. for 5 hours to produce Ud 2 pellets containing Gd 2 O 3 .
得られたGd2O3入りUO2ペレットの平均結晶粒径および
焼結密度を測定し、これらの測定結果を第１表に示し
た。The resulting Gd 2 O 3 containing UO 2 measures the average crystal grain size and sintering density of the pellets, showed results of these measurements are given in Table 1.
上記実施例の結果から、この発明においてGd2O3入りU
O2粉末にアルミニウム化合物を、アルミニウムに換算し
て1000〜5000ppm（0.1〜0.5重量％）添加すること添加
することにより、容易にGd2O3入り二酸化ウランペレッ
トの結晶粒径を大きくすることができるが、比較例１に
もみられるように0.5重量％（5000ppm）を越えて含有し
ても平均結晶粒径はそれ以上大きくはならず、かえって
小さくなることがわかる。From the results of the above examples, it can be seen that U containing Gd 2 O 3 in the present invention.
By adding an aluminum compound to O 2 powder in an amount of 1000 to 5000 ppm (0.1 to 0.5% by weight) in terms of aluminum, the crystal grain size of the uranium dioxide pellet containing Gd 2 O 3 can be easily increased. However, as can be seen from Comparative Example 1, even if the content exceeds 0.5% by weight (5000 ppm), the average crystal grain size does not increase any more, but rather decreases.
なお、この実施例ではアルミニウムの添加に酸化アル
ミニウムを用いたが、アルミニウムの添加は酸化アルミ
ニウムに限定されるものではなく、その他、水酸化アル
ミニウム、脂肪酸のアルミニウム塩（例えば、ステアリ
ン酸アルミニウム、パルミチン酸アルミニウムおよびオ
レイン酸アルミニウム）などにより添加することができ
る。In this example, aluminum oxide was used for the addition of aluminum. However, the addition of aluminum is not limited to aluminum oxide. In addition, aluminum hydroxide, aluminum salts of fatty acids (for example, aluminum stearate, palmitic acid) Aluminum and aluminum oleate).
Claims (1)
配合し、混合し、成形し、焼結して酸化ガドリニウム入
り核燃料を製造する方法において、 アルミニウム化合物を、アルミニウムに換算して1000〜
5000ppm（0.1〜0.5重量％）添加することを特徴とする
大結晶粒径を有する酸化ガドリニウム入り核燃料ペレッ
トの製造方法。1. A method of producing a gadolinium oxide-containing nuclear fuel by blending a predetermined amount of gadolinium oxide with uranium oxide, mixing, molding and sintering, wherein the aluminum compound is converted to aluminum in an amount of 1,000 to 1,000.
A method for producing nuclear fuel pellets containing gadolinium oxide having a large crystal grain size, wherein 5000 ppm (0.1 to 0.5% by weight) is added.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1058421A JP2655908B2 (en) | 1989-03-10 | 1989-03-10 | Method for producing nuclear fuel pellet containing gatolinium oxide having large crystal grain size |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1058421A JP2655908B2 (en) | 1989-03-10 | 1989-03-10 | Method for producing nuclear fuel pellet containing gatolinium oxide having large crystal grain size |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02236490A JPH02236490A (en) | 1990-09-19 |
| JP2655908B2 true JP2655908B2 (en) | 1997-09-24 |
Family
ID=13083916
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1058421A Expired - Lifetime JP2655908B2 (en) | 1989-03-10 | 1989-03-10 | Method for producing nuclear fuel pellet containing gatolinium oxide having large crystal grain size |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2655908B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2860638A1 (en) * | 2003-10-06 | 2005-04-08 | Commissariat Energie Atomique | PROCESS FOR MANUFACTURING PELLETS OF NUCLEAR FUEL BASED ON MIXED (U, PU) O2 OR (U, TH) O2 OXIDE FUEL |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6097294A (en) * | 1983-10-06 | 1985-05-31 | シーメンス、アクチエンゲゼルシヤフト | Manufacture of oxide group nuclear fuel sintered body |
| JPS6236589A (en) * | 1985-08-12 | 1987-02-17 | 日本ニユクリア・フユエル株式会社 | Manufacture of nuclear-fuel sintered body containing gadolinium oxide |
| JPH01248092A (en) * | 1988-03-29 | 1989-10-03 | Mitsubishi Nuclear Fuel Co Ltd | Manufacture of nuclear fuel pellet |
-
1989
- 1989-03-10 JP JP1058421A patent/JP2655908B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH02236490A (en) | 1990-09-19 |
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