JP3012671B2 - Method for producing nuclear fuel pellets - Google Patents
Method for producing nuclear fuel pelletsInfo
- Publication number
- JP3012671B2 JP3012671B2 JP2205042A JP20504290A JP3012671B2 JP 3012671 B2 JP3012671 B2 JP 3012671B2 JP 2205042 A JP2205042 A JP 2205042A JP 20504290 A JP20504290 A JP 20504290A JP 3012671 B2 JP3012671 B2 JP 3012671B2
- Authority
- JP
- Japan
- Prior art keywords
- powder
- sintering
- nuclear fuel
- pellets
- cao
- 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 - Fee Related
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
Description
【発明の詳細な説明】 ［産業上の利用分野］ 本発明は、酸化物燃料ペレットの製造方法に係り、酸
化物燃料粉末に焼結剤を添加してペレットの結晶粒を改
善した、信頼性の高い核燃料ペレットの製造方法に関す
る。Description: FIELD OF THE INVENTION The present invention relates to a method for producing oxide fuel pellets, in which a sintering agent is added to oxide fuel powder to improve the crystal grains of the pellet, and the reliability is improved. The present invention relates to a method for producing nuclear fuel pellets having a high density.
［従来の技術］ 軽水炉あるいは高速増殖炉に装荷される核燃料ペレッ
トは、発電炉において経験された最も高い燃機度までそ
の健全性が確認されている。しかし、現在計画されてい
る燃料の高燃焼度化に伴つて、結晶粒界に析出したFP
（核***生成物）ガスによる気泡スエリングの増加に伴
うペレットと被覆管の機械的相互作用（PCI）の増大、
燃料からの核***生成ガス放出による燃料棒内の内圧上
昇が起こり、燃料の健全性が失われる可能性があり、現
在使用されているペレットを改善する必要がある。[Prior Art] The soundness of nuclear fuel pellets loaded in a light water reactor or a fast breeder reactor has been confirmed up to the highest flammability experienced in a power reactor. However, with the currently planned high burnup of fuel, FP precipitated at grain boundaries
Increase of mechanical interaction (PCI) between pellet and cladding tube due to increase of bubble swelling by (fission product) gas,
Internal pressure buildup in the fuel rods due to release of fission gas from the fuel can cause loss of fuel integrity, and there is a need to improve the pellets used today.
そこで、従来では、ペレットからの核***生成ガス放
出率が核***生成ガスのペレット結晶粒内の拡散に律速
されると考え、ペレットの結晶粒径を大きくすることに
よって、核***生成ガスの放出率を抑える方法が試みら
れてきた。Therefore, conventionally, it is considered that the fission gas release rate from the pellet is determined by the diffusion of the fission gas in the pellet crystal grains, and the release rate of the fission gas is suppressed by increasing the crystal grain size of the pellet. Methods have been tried.
しかし、結晶粒径を大きくするとペレットのクリープ
速度が低下し、PCIに悪影響を及ぼす可能性がある。However, increasing the grain size decreases the creep rate of the pellet, which can adversely affect PCI.
一方、ペレットのクリープ速度を向上させる方法とし
て、二酸化ウラン粉末にアルミニウム酸化物とケイ素酸
化物からなる焼結剤を添加し、結晶粒界に軟質第二相を
析出させる方法が考えられた（特開平１−193691号公
報）。On the other hand, as a method of improving the creep rate of the pellet, a method of adding a sintering agent composed of aluminum oxide and silicon oxide to uranium dioxide powder and precipitating a soft second phase at the crystal grain boundaries has been considered. JP-A-1-193691).
この結晶粒界に軟質相を析出させる方法として、天然
に存在する粘土鉱物を添加する方法、あるいは高純度の
ケイ素酸化物、アルミニウム酸化物等の粉末を任意の組
成で混合し、添加する方法が考えられる。これらの焼結
剤を添加し焼結することにより、液相焼結メカニズムに
よって二酸化ウラン粉末間の表面反応を促進し、結晶粒
の成長を助長すると共に、アルミナシリケートのガラス
相が粒界に析出しペレットが軟質化する。As a method of precipitating a soft phase at the crystal grain boundaries, a method of adding a naturally occurring clay mineral, or a method of mixing and adding a powder of high-purity silicon oxide, aluminum oxide, or the like with an arbitrary composition is used. Conceivable. By adding these sintering agents and sintering, the surface reaction between uranium dioxide powder is promoted by the liquid phase sintering mechanism, which promotes the growth of crystal grains, and the glass phase of alumina silicate precipitates at the grain boundaries. The pellet softens.
［発明が解決しようとする課題］ しかし、上記の方法では可燃性毒性であるGd2O3を含
む核燃料ペレットを製作する場合には、不適当であるこ
とが分つた。以下にその理由を述べる。[Problems to be Solved by the Invention] However, it has been found that the above method is not suitable for producing nuclear fuel pellets containing Gd 2 O 3 which is flammable and toxic. The reason is described below.
一般に、Gd2O3とUO2との混合酸化物はUO2に比べ焼結
性が低く、同一焼結条件下ではその結晶ペレットの密
度、結晶粒径は共にUO2焼結ペレットよりも小さくなる
ことが知られている。Generally, mixed oxides of Gd 2 O 3 and UO 2 have lower sinterability than UO 2, and under the same sintering conditions, the density and crystal grain size of the crystal pellets are both smaller than that of UO 2 sintered pellets Is known to be.
また、水素気流中で焼結を行なった場合には、ペレッ
トに多くのマイクロクラックが発生する問題が生じる。Further, when sintering is performed in a hydrogen stream, there is a problem that many micro cracks are generated in the pellet.
そこで上記問題点を解決するために、Gd2O3漆加UO
2は、通常、湿性水素雰囲気あるいは二酸化炭素と一酸
化炭素との混合気体雰囲気下において比較的高温（1700
℃以上）で焼結される。Therefore, to solve the above problems, Gd 2 O 3 Urika UO
2 is usually a relatively high temperature (1700) in a humid hydrogen atmosphere or a mixed gas atmosphere of carbon dioxide and carbon monoxide.
℃ or more).
一方、アルミニウム酸化物とケイ素酸化物からなる焼
結剤は、上記焼結条件下では有効に作用せず、ペレット
内に粗大気孔（おそらくはケイ素酸化物の蒸発による）
を生成し、ペレットの密度を小さくしてしまうことがわ
かった。さらにGd2O3漆加UO2ペレットに対して粒の成長
促進効果がほとんど無いこともわかった。On the other hand, the sintering agent consisting of aluminum oxide and silicon oxide does not work effectively under the above sintering conditions, and coarse pores (probably due to evaporation of silicon oxide) in the pellet.
Was produced, and the density of the pellet was reduced. Furthermore, it was also found that the Gd 2 O 3 lacquered UO 2 pellets had almost no effect of promoting the growth of grains.
また、燃料の高焼結度化に伴つて、Gd2O3添加ペレッ
トの燃料に占める割合およびその添加量も増加する傾向
にある。従つて、Gd2O3添加UO2燃料についてもUO2燃料
と同様に、FPガスの放出を減少させる効果を有し、か
つ、クリープ特性が優れたペレットの開発が必要とされ
る。Further, as the degree of sintering of the fuel increases, the ratio of the pellets added with Gd 2 O 3 to the fuel and the amount of the added pellets also tend to increase. Therefore, similarly to the UO 2 fuel, the development of pellets having the effect of reducing the emission of FP gas and having excellent creep properties is required for the Gd 2 O 3 -added UO 2 fuel.
本発明は、かかる問題点を解決するためになされたも
のであり、酸化物燃料ペレットの結晶粒径を粗大化し、
結晶粒界に析出第２相を生成するようにしたものであ
る。The present invention has been made in order to solve such a problem, the crystal grain size of the oxide fuel pellets are coarsened,
The second phase precipitates at the crystal grain boundaries.
［課題を解決するための手段］ 上記課題を解決する本発明の核燃料ペレットの製造方
法は次のとおりである。[Means for Solving the Problems] The method for producing nuclear fuel pellets of the present invention for solving the above problems is as follows.
二酸化ウラン粉末を含む混合酸化物粉末を圧縮成形
後、焼結する核燃料ペレットの製造方法において、 前記混合酸化物粉末に、CaOとAl2O3からなる焼結剤を
混合し、圧粉成形したグリーンペレットを1,500〜1,800
℃で焼結するものである。After compression-molding the mixed oxide powder containing uranium dioxide powder, in the method for producing nuclear fuel pellets to be sintered, the mixed oxide powder was mixed with a sintering agent composed of CaO and Al 2 O 3 and compacted. Green pellets from 1,500 to 1,800
Sintered at ℃.
［作用］ 二酸化ウランを含む混合酸化物に約25〜65wt％のCaO
と残部Al2O3とから成る組成を有する焼結剤、または、
後記焼結温度（1,500℃）より低い温度で熱分解する焼
結剤の前駆物質（例えばCaCO3）を混合することによ
り、混合酸化物と焼結剤との合計量を基準として約0.1
〜約1.0wt％の割合で前記焼結剤を含有する混合物を調
製する。[Action] About 25 to 65 wt% of CaO to mixed oxide containing uranium dioxide
And a sintering agent having a composition consisting of the balance Al 2 O 3 , or
By mixing a precursor (for example, CaCO 3 ) of a sintering agent that thermally decomposes at a temperature lower than the sintering temperature (1,500 ° C.), about 0.1% based on the total amount of the mixed oxide and the sintering agent is mixed.
A mixture containing the sintering agent in a proportion of about 1.0 wt% is prepared.
これを成形して圧縮体とし、前記焼結剤が液相を成す
ような温度、すなわち、1500℃〜1800℃の範囲内の温度
で前記圧縮体を焼結すれば、焼結中の焼結剤は一液相の
共融体となり、液相焼結メカニズムによって核燃料粉末
間の表面反応を促進し、結晶粒の成長を助長する。この
結晶粒の成長によってFPガスの結晶粒界への拡散距離が
増加し、ペレットからのFPガス放出率が低下する。This is molded into a compact, and the sintered body is sintered at a temperature at which the sintering agent forms a liquid phase, that is, at a temperature in the range of 1500 ° C to 1800 ° C. The agent becomes a eutectic in one liquid phase and promotes a surface reaction between nuclear fuel powders by a liquid phase sintering mechanism, thereby promoting the growth of crystal grains. Due to the growth of the crystal grains, the diffusion distance of the FP gas to the crystal grain boundaries increases, and the FP gas release rate from the pellets decreases.
また、上記焼結剤の一部は焼結中に蒸発し、ペレット
外に放出されるが、一部は核燃料の結晶マトリクスに固
溶し、他は結晶粒界に第二相として析出する。この析出
相は比較的低い融点を有するため、軟化温度が低く、ペ
レットのクリープ速度を向上させ、耐PCI性を向上させ
る。Further, a part of the sintering agent evaporates during sintering and is released outside the pellet, but a part of the sintering agent dissolves in the crystal matrix of the nuclear fuel, and the other precipitates as a second phase at the crystal grain boundary. Since the precipitated phase has a relatively low melting point, the softening temperature is low, the creep rate of the pellet is improved, and the PCI resistance is improved.
［実施例］ 以下本発明の一実施例を第１図を用いて説明する。Embodiment An embodiment of the present invention will be described below with reference to FIG.
第１図は、本発明の核燃料ペレットの製造方法を示す
工程図である。１はAl2O3、２はCaO、３は粗混合、４は
焼結剤、５は二酸化ウラン粉末、６は酸化ガドリニウム
粉末、７は混合Ｉ、８は混合II、９は潤滑剤、10は圧粉
成形、11は脱脂、12は焼結である。以下に、第１図の動
作につき説明する。FIG. 1 is a process chart showing a method for producing nuclear fuel pellets of the present invention. 1 is Al 2 O 3 , 2 is CaO, 3 is a rough mixture, 4 is a sintering agent, 5 is a uranium dioxide powder, 6 is a gadolinium oxide powder, 7 is a mixture I, 8 is a mixture II, 9 is a lubricant, 10 Is powder compaction, 11 is degreasing, and 12 is sintering. The operation of FIG. 1 will be described below.
まず、Al2O3の1.50wt％とCaOの2.50wt％（最終の混合
粉末全重量に対する比率）とを粗混合３し、これを８％
−H2/N2混合ガス気流中で1550℃まで加熱して溶解させ
た後冷却し、均質なアルミン酸カルシウムを得た。これ
を粉砕して均一な粉末とした。First, 1.50 wt% of Al 2 O 3 and 2.50 wt% of CaO (ratio to the total weight of the final mixed powder) were roughly mixed 3 and this was mixed with 8%
The mixture was heated to 1550 ° C. in a mixed gas stream of -H 2 / N 2 to dissolve and then cooled to obtain homogeneous calcium aluminate. This was pulverized into a uniform powder.
この粉末を焼結剤として工程図に従い、核燃料ペレッ
トを製造した。すなわち、二酸化ウラン（UO2）粉末５
に上記焼結剤４を混合７（混合Ｉ）した後、酸化ガドリ
ウニム（Gd2O3）粉末６を添加し、さらに潤滑剤９を加
えて混合８（混合II）し、圧粉成形10しグリーンペレッ
トとした。Using this powder as a sintering agent, nuclear fuel pellets were produced according to the process chart. That is, uranium dioxide (UO 2 ) powder 5
After mixing 7 (mixing I) with the above sintering agent 4, gadolinium oxide (Gd 2 O 3 ) powder 6 was added, and further a lubricant 9 was added and mixed 8 (mixing II), followed by compacting 10. Green pellets were obtained.
上記焼結剤４およびGd2O3の添加量はUO2、Gd2O3およ
び上記焼結剤４の合計量を基準としてそれぞれ0.25wt％
および10wt％とした。The amounts of the sintering agent 4 and Gd 2 O 3 added are each 0.25 wt% based on the total amount of UO 2 , Gd 2 O 3 and the sintering agent 4.
And 10 wt%.
ここにGd2O3粉末（最大10wt％）を添加したのは、Gd2
O3が加わると結晶粒の成長促進にマイナスの効果がある
ことが知られているためにあえてこれを添加し、本発明
の効果を立証するものである。Here was added Gd 2 O 3 powder (up to 10 wt%) is, Gd 2
It is known that the addition of O 3 has a negative effect on promoting the growth of crystal grains, so that it is added to prove the effect of the present invention.
次に、このグリーンペレットを脱脂工程11に付した
後、湿性水素雰囲気中で1760℃、５時間焼結12した。Next, this green pellet was subjected to a degreasing step 11, and then sintered 12 at 1760 ° C. for 5 hours in a humid hydrogen atmosphere.
なお、第１図に示した工程図中、潤滑剤９の混合およ
び脱脂11の工程は省略してもよい。また、前記焼結剤は
CaO粉末とAl2O3粉末との混合物を融解または固相焼結
後、粉砕したものを用いたが、同組成の化合物を用いる
こともできる。In the process diagram shown in FIG. 1, the steps of mixing and degreasing the lubricant 9 may be omitted. The sintering agent is
Although a mixture of CaO powder and Al 2 O 3 powder is melted or solid-phase sintered and then pulverized, a compound having the same composition can be used.
上記実施例では、焼結雰囲気ガスとして湿性水素ガス
を用いたが、一酸化炭素と二酸化炭素との混合ガスを用
いてもよい。また、焼結剤としてAl2O3粉末とCaO粉末の
混合粉末あるいはAl2O3粉末と水酸化カルシウム（Ca（O
H）２）または炭酸カルシウム（CaCO3）粉末との混合粉
末を用いてもよい。In the above embodiment, a wet hydrogen gas was used as the sintering atmosphere gas, but a mixed gas of carbon monoxide and carbon dioxide may be used. As a sintering agent, a mixed powder of Al 2 O 3 powder and CaO powder or an Al 2 O 3 powder and calcium hydroxide (Ca (O
H) 2 ) or a mixed powder with calcium carbonate (CaCO 3 ) powder may be used.
第２図は、本発明および従来法によって製造した核燃
料ペレット断面の顕微鏡組織写真の模式図である。FIG. 2 is a schematic view of a microstructure photograph of a cross section of a nuclear fuel pellet manufactured by the present invention and a conventional method.
すなわち、第２図（ａ）は本実施例の方法により製造
した核燃料ペレット（焼結剤はアルミン酸カルシウ
ム）、第２図（ｂ）は焼結剤として均一なアルミナシリ
ケートを用いて製造した核燃料ペレット、第２図（ｃ）
は、焼結剤を使用せず製造した核燃料ペレットの断面を
示す顕微鏡組織写真の模式図である。That is, FIG. 2 (a) is a nuclear fuel pellet (sintering agent is calcium aluminate) manufactured by the method of the present embodiment, and FIG. 2 (b) is a nuclear fuel manufactured using uniform alumina silicate as the sintering agent. Pellets, FIG. 2 (c)
FIG. 3 is a schematic view of a microstructure photograph showing a cross section of a nuclear fuel pellet manufactured without using a sintering agent.
第２図（ａ）におけるペレットの結晶粒径は、約50μ
ｍであり、（ｂ）、（ｃ）におけるペレットの結晶粒径
よりも明らかに大きいことがわかる。The crystal grain size of the pellet in FIG.
m, which is clearly larger than the crystal grain size of the pellets in (b) and (c).
また、第２図（ａ）においては、結晶粒界が太くなっ
ている個所が認められ、これらを走査型電顕による解析
にかけると、アルミン酸カルシウム相が確認された。Further, in FIG. 2 (a), portions where the crystal grain boundaries became thick were observed, and when these were analyzed by a scanning electron microscope, a calcium aluminate phase was confirmed.
本実施例の方法により、二酸化ウランの他に、酸化ガ
ドリウムが混在した場合にも、核燃料ペレットの結晶粒
の粗大化を促進することが認められた。According to the method of this example, it was recognized that even when gadolinium oxide was present in addition to uranium dioxide, the coarsening of the crystal grains of the nuclear fuel pellets was promoted.
［発明の効果］ 本発明によれば、混合酸化物核燃料ペレットの大粒径
化と結晶粒界の軟質化によるクリープ特性の向上を同時
に達成でき、FPガス放出率低減と耐PCI性能の向上を達
成できるので、核燃料ペレット開発の将来性について見
通しを得ることができた。[Effects of the Invention] According to the present invention, it is possible to simultaneously achieve an increase in the grain size of the mixed oxide nuclear fuel pellets and an improvement in the creep characteristics due to the softening of the crystal grain boundaries, thereby reducing the FP gas emission rate and improving the anti-PCI performance. As a result, we gained insight into the future of nuclear fuel pellet development.
第１図は本発明による核燃料ペレット製造方法の一実施
例を示す工程図、第２図は本発明による核燃料ペレット
断面と従来方法による核燃料ペレット断面とを比較した
金属組織の顕微鏡写真の模式図である。 ＜符号の説明＞ １……Al2O3、２……CaO、３……粗混合、４……焼結
剤、５……二酸化ウラン粉末、６……酸化ガドリニウム
粉末、７……混合Ｉ、８……混合II、９……潤滑剤、10
……圧粉成形、11……脱脂、12……焼結。FIG. 1 is a process diagram showing one embodiment of the nuclear fuel pellet manufacturing method according to the present invention, and FIG. 2 is a schematic view of a micrograph of a metal structure comparing a nuclear fuel pellet cross section according to the present invention with a nuclear fuel pellet cross section according to a conventional method. is there. <Description of References> 1... Al 2 O 3 , 2... CaO 3... Rough mixing 4... Sintering agent 5... Uranium dioxide powder 6... Gadolinium oxide powder 7. , 8 ... mix II, 9 ... lubricant, 10
…… Pressing, 11… Degreasing, 12… Sintering.
───────────────────────────────────────────────────── フロントページの続き (58)調査した分野(Int.Cl.7，ＤＢ名) G21C 3/62 ＪＩＣＳＴ（ＪＯＩＳ)──────────────────────────────────────────────────続 き Continued on front page (58) Field surveyed (Int.Cl. 7 , DB name) G21C 3/62 JICST (JOIS)
Claims (6)
圧縮成形後、焼結する核燃料ペレットの製造方法におい
て、 前記混合酸化物粉末に、CaOとAl2O3からなる焼結剤を混
合し、圧粉成形したグリーンペレットを1,500〜1,800℃
で焼結することを特徴とする核燃料ペレットの製造方
法。1. A method for producing nuclear fuel pellets, comprising sintering a mixed oxide powder containing uranium dioxide powder after compression molding, wherein a sintering agent comprising CaO and Al 2 O 3 is mixed with the mixed oxide powder. Green compacted green pellets at 1,500 ~ 1,800 ℃
A method for producing nuclear fuel pellets, characterized by sintering.
とからなる請求項１に記載の核燃料ペレットの製造方
法。2. The sintering agent comprises 25 to 65% by weight of CaO and the balance of Al 2 O 3
The method for producing nuclear fuel pellets according to claim 1, comprising:
合物、または、CaO粉末とAl2O3粉末との混合物を融解し
た共融体または固相焼結した焼結体で、これらを粉砕し
たものである請求項１または２に記載の核燃料ペレット
の製造方法。Wherein said sintered Yuizai is a mixture of CaO powder and Al 2 O 3 powder, or sintered who eutectic or solid phase sintering to melt the mixture of CaO powder and Al 2 O 3 powder The method for producing nuclear fuel pellets according to claim 1 or 2, wherein these are pulverized in a body.
ムまたは水酸化カルシウムである請求項１に記載の核燃
料ペレットの製造方法。4. The method according to claim 1, wherein the precursor of the sintering agent CaO is calcium carbonate or calcium hydroxide.
雰囲気中または二酸化炭素と一酸化炭素との混合気体雰
囲気中で行なう請求項１に記載の核燃料ペレットの製造
方法。5. The method according to claim 1, wherein the sintering of the green pellets is performed in a humid hydrogen atmosphere or a mixed gas atmosphere of carbon dioxide and carbon monoxide.
wt％以上含む請求項１に記載の核燃料ペレットの製造方
法。6. The mixed oxide powder according to claim 1, wherein the uranium dioxide is 90%.
The method for producing nuclear fuel pellets according to claim 1, wherein the content is at least wt%.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2205042A JP3012671B2 (en) | 1990-08-03 | 1990-08-03 | Method for producing nuclear fuel pellets |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2205042A JP3012671B2 (en) | 1990-08-03 | 1990-08-03 | Method for producing nuclear fuel pellets |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0493695A JPH0493695A (en) | 1992-03-26 |
| JP3012671B2 true JP3012671B2 (en) | 2000-02-28 |
Family
ID=16500488
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2205042A Expired - Fee Related JP3012671B2 (en) | 1990-08-03 | 1990-08-03 | Method for producing nuclear fuel pellets |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3012671B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101839320B1 (en) * | 2016-02-25 | 2018-04-27 | 한전원자력연료 주식회사 | The composition and manufacturing method of large grain UO pellet |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5786611A (en) * | 1995-01-23 | 1998-07-28 | Lockheed Idaho Technologies Company | Radiation shielding composition |
| KR100521638B1 (en) * | 2002-10-02 | 2005-10-13 | 한국원자력연구소 | Uranium dioxide fuel containing SiO2-CaO-Cr2O3 and thereof method |
| CN111334859B (en) * | 2020-04-06 | 2021-04-20 | 上海应用技术大学 | Method for growing uranium dioxide crystal by using alumina fluxing agent |
-
1990
- 1990-08-03 JP JP2205042A patent/JP3012671B2/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101839320B1 (en) * | 2016-02-25 | 2018-04-27 | 한전원자력연료 주식회사 | The composition and manufacturing method of large grain UO pellet |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0493695A (en) | 1992-03-26 |
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