JPS63249096A - Manufacture of nuclear fuel pellet - Google Patents
Manufacture of nuclear fuel pelletInfo
- Publication number
- JPS63249096A JPS63249096A JP62082960A JP8296087A JPS63249096A JP S63249096 A JPS63249096 A JP S63249096A JP 62082960 A JP62082960 A JP 62082960A JP 8296087 A JP8296087 A JP 8296087A JP S63249096 A JPS63249096 A JP S63249096A
- Authority
- JP
- Japan
- Prior art keywords
- sintering
- density
- atmosphere
- pellets
- nuclear fuel
- 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.)
- Granted
Links
- 239000008188 pellet Substances 0.000 title claims description 39
- 238000004519 manufacturing process Methods 0.000 title claims description 9
- 239000003758 nuclear fuel Substances 0.000 title claims description 9
- 238000005245 sintering Methods 0.000 claims description 33
- 238000000034 method Methods 0.000 claims description 12
- 239000000843 powder Substances 0.000 claims description 10
- 239000011148 porous material Substances 0.000 claims description 9
- 239000002994 raw material Substances 0.000 claims description 8
- 238000000465 moulding Methods 0.000 claims description 6
- 239000007789 gas Substances 0.000 claims description 5
- 239000011159 matrix material Substances 0.000 claims description 5
- 239000011261 inert gas Substances 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 3
- 239000013078 crystal Substances 0.000 description 6
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 5
- 238000007796 conventional method Methods 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 229910052751 metal Inorganic materials 0.000 description 3
- 239000002184 metal Substances 0.000 description 3
- 238000001000 micrograph Methods 0.000 description 3
- 239000000203 mixture Substances 0.000 description 3
- -1 uranium ions Chemical class 0.000 description 3
- 238000004438 BET method Methods 0.000 description 2
- 230000004913 activation Effects 0.000 description 2
- 238000000227 grinding Methods 0.000 description 2
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 230000001737 promoting effect Effects 0.000 description 2
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical class [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000005056 compaction Methods 0.000 description 1
- 230000000052 comparative effect Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000000748 compression moulding Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 229910001938 gadolinium oxide Inorganic materials 0.000 description 1
- 229940075613 gadolinium oxide Drugs 0.000 description 1
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(iii) oxide Chemical compound [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 description 1
- 238000005469 granulation Methods 0.000 description 1
- 230000003179 granulation Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000011812 mixed powder Substances 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 238000010298 pulverizing process Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- ZCUFMDLYAMJYST-UHFFFAOYSA-N thorium dioxide Chemical compound O=[Th]=O ZCUFMDLYAMJYST-UHFFFAOYSA-N 0.000 description 1
- 229910003452 thorium oxide Inorganic materials 0.000 description 1
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
- Processing And Handling Of Plastics And Other Materials For Molding In General (AREA)
- Inorganic Compounds Of Heavy Metals (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】
〔発明の技術分野〕
本発明は、核燃料ペレットに関し、特に高速増殖炉用に
好適な核燃料ペレットの製造方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to nuclear fuel pellets, and particularly to a method for producing nuclear fuel pellets suitable for fast breeder reactors.
従来、ＵＯっやＵ Ｏ２とＰ ｕ Ｏ２の混合物ペレッ
ト（以下ペレットと略称する）を低密度（理論密度の９
０％以下）で焼結するためには、焼結を還元雰囲気下（
Ｈ２２成分）低温度（通常１６００℃以下）で行なうこ
とが有効であることは既に知られている。しかしながら
、このような還元雰囲気下において低温度で焼結したペ
レットは、焼きしまりの値が高く、照射挙動に着目する
と、コラップスやペレット温度上昇によるＦＰガス放出
量の増大等の問題が生ずる点で好ましくない。したがっ
て、これらの問題を防止するためには、高温度（通常１
６００℃以上）で還元雰囲気下焼結して低密度を得る為
には、適当二のポア・フォーマーを原料に添加すること
が必要となる。Conventionally, pellets of a mixture of UO2 and P u O2 (hereinafter referred to as pellets) have been processed to a low density (theoretical density of 9).
0% or less), sintering must be carried out under a reducing atmosphere (
H22 component) It is already known that it is effective to carry out the reaction at a low temperature (usually 1600° C. or lower). However, pellets sintered at low temperatures in such a reducing atmosphere have a high sintering value, and when focusing on irradiation behavior, problems such as collapse and an increase in the amount of FP gas released due to increase in pellet temperature occur. Undesirable. Therefore, to prevent these problems, high temperatures (usually 1
In order to obtain a low density by sintering in a reducing atmosphere at temperatures above 600°C, it is necessary to add an appropriate number of pore formers to the raw material.
しかし、ポア・フォーマー等の付加的成分を添加するこ
とは、その添加工程や、焼結前の脱ボア・フォーマ一工
程が必要となり、商業ベースから考えると、コストの増
大をもたらし、また工程も繁雑化する。However, adding additional components such as pore formers requires an addition process and a debore former process before sintering, which increases costs from a commercial perspective and also increases the process time. It becomes complicated.
本発明は上述した点に鑑みてなされたものであり、製造
工程が簡略化されるとともに、微細構造ならびに燃焼特
性にすぐれた高速炉用低密度ペレットを製造する方法を
提供することを目的としている。The present invention has been made in view of the above points, and an object of the present invention is to provide a method for manufacturing low-density pellets for fast reactors, which simplifies the manufacturing process and has excellent microstructure and combustion characteristics. .
このような目的を達成するため、本発明に係る核燃料ペ
レットの製造方法は、原料粉末を成形したのち、この成
形体を焼結し、さらにその後にこの焼結体を還元雰囲気
中で処理することにより核燃料ペレットを製造するに際
し、前記成形体はポア・フォーマーを含まず、かつ、焼
結雰囲気としてペレットマトリックスへの溶解度が低く
しかも低温度で焼結が開始するような雰囲気中で焼結を
行なうことを特徴としている。In order to achieve such an object, the method for producing nuclear fuel pellets according to the present invention includes molding raw material powder, sintering this molded body, and then processing this sintered body in a reducing atmosphere. When producing nuclear fuel pellets, the compact is sintered in an atmosphere that does not contain pores or formers and that has low solubility in the pellet matrix and that sintering starts at a low temperature. It is characterized by
このように本発明によれば、高速炉用低密度ペレット燃
料（理論密度の８０〜９０％）を製造するに際し、従来
のポア・フォーマーを用いて密度をコントロールする方
法にかわって、ポア・フォーマーを用いずしかも低密度
のペレットを製造することができる。この方法を適用す
れば、ポア・フォーマー添加工程が省略できるので、工
程が簡略化されるとともに、コストの低減化を図ること
ができる。As described above, according to the present invention, when producing low-density pellet fuel for fast reactors (80 to 90% of the theoretical density), instead of the conventional method of controlling density using a pore former, a pore former is used. It is possible to produce low-density pellets without using the method. If this method is applied, the pore former addition step can be omitted, so the process can be simplified and costs can be reduced.
まな前述したように、ポア・フォーマーなしで低密度を
得るためには、低温度還元雰囲気下（通常１６００℃以
下）で焼結を行なえば可能であることは従来知られてい
るが、このようにして焼結されたペレットは、焼きしま
りが大きく、前述した問題点が生じる。本発明の方法に
おいては、これを防止するため、比較的高温度（１６０
０℃以上）で焼結することができ、しかも低密度化を達
成することができる。As mentioned above, it has been known that it is possible to obtain low density without pore formers by sintering in a low-temperature reducing atmosphere (usually below 1600°C); The pellets sintered in this manner have large sintering, resulting in the above-mentioned problems. In the method of the present invention, in order to prevent this, relatively high temperatures (160
It is possible to sinter at a temperature of 0° C. or higher) and to achieve low density.
また、従来法で得られるペレットの結晶粒径は通常１０
〜２０μｍであるが、本発明によれば、大結晶粒径（４
０μｍ以上）のペレットを得ることができるので、ＦＰ
ガス放出量の低減化においてもすぐれている。In addition, the crystal grain size of pellets obtained by conventional methods is usually 10
~20 μm, but according to the present invention, the large grain size (4
FP
It is also excellent in reducing the amount of gas released.
以下、本発明を更に具体的に説明する。 The present invention will be explained in more detail below.
本発明で用いられる核燃料原料粉末としては、二酸化ウ
ランその他の酸化ウラン、酸化プルトニウム、酸化トリ
ウム等の１種または２種以上が用いられ、さらにこの他
に中性子吸収物質として酸化ガドリニウムを加えた混合
物も用いられ得る。As the nuclear fuel raw material powder used in the present invention, one or more types of uranium dioxide, other uranium oxides, plutonium oxide, thorium oxide, etc. are used, and in addition to these, a mixture containing gadolinium oxide as a neutron absorbing substance is also used. can be used.
これらの原料粉末は、焼結工程での粒成長をより促進さ
せるためには、ボールミル、振動ボールミル、ジェット
ミル等で平均粒径０．１〜１．０μｍ（ＢＥＴ法による
計算値）まで微粉砕を行なうことが好ましい。これらの
粉末を成形し、焼結すると、微粉砕された粉末は比較的
活性であるため、通常の粉末より更に低温度で焼結が開
始し、粒成長および密度低下を促進する上で好ましい。In order to further promote grain growth in the sintering process, these raw material powders are pulverized to an average particle size of 0.1 to 1.0 μm (value calculated by the BET method) using a ball mill, vibrating ball mill, jet mill, etc. It is preferable to do this. When these powders are compacted and sintered, the pulverized powders are relatively active, so sintering begins at a lower temperature than normal powders, which is favorable for promoting grain growth and density reduction.
次いで、このようにして得られた原料粉末を常法に従い
、所望形状の成形機の金型中に装入し、例えば０．５〜
５ Ｌｏｎ／ｃＩ＃程度の圧力で成形して、４０〜６０
％ＴＤ（理論密度の４０％〜６０％、理論密度は二酸化
ウランの場合１０．９５ｇ／ｃＩ＃）の成形体を得る。Next, the raw material powder thus obtained is charged into a mold of a molding machine having a desired shape according to a conventional method, and
5 Molding with a pressure of about Lon/cI#, 40 to 60
%TD (40% to 60% of theoretical density, theoretical density is 10.95 g/cI# for uranium dioxide).
次いで、このようにして得られた成形体を焼結する。Next, the molded body thus obtained is sintered.
本発明における特徴のひとつは、粒成長を促進させ、か
つ、粒成長時に粒界に集合したボアでペレット密度を低
下させるために、焼結雰囲気として、ペレットマトリッ
クスへの溶解度が小さく、かつ低温度で焼結を開始させ
ることができる雰囲気を使用することである。One of the features of the present invention is that the sintering atmosphere has a low solubility in the pellet matrix and a low temperature in order to promote grain growth and reduce pellet density due to the bores that gather at the grain boundaries during grain growth. The first step is to use an atmosphere that can initiate sintering.
このような雰囲気として有効なガスとしては、ＣＯ２お
よび（または）水蒸気があり、更にこれらのガスにＡ
ｒ ｓ Ｎ ２等の不活性ガスと混合することがより好
ましい。この場合、混合比は、ＣＯ２または（および）
水蒸気１００〜６０％、不活性ガス０〜４０９６が好ま
しい。Gases that are effective as such an atmosphere include CO2 and/or water vapor, and these gases also contain A
More preferably, it is mixed with an inert gas such as r s N 2 . In this case, the mixing ratio is CO2 or (and)
Water vapor 100-60% and inert gas 0-4096% are preferred.
焼結条件としては、１６００〜１８００℃、２〜４時間
が最も好ましい。１６００°Ｃ未満では、粒成長が十分
でなく、所望の焼結密度（理論密度の８０〜９０％）よ
り高密度となり、一方、１８００℃を超えると、焼結雰
囲気中に含まれる０２の影響でＵＤ２の酸化および蒸発
がはげしくなるので好ましくない。The most preferred sintering conditions are 1600 to 1800°C for 2 to 4 hours. Below 1600°C, grain growth is insufficient and the sintered density becomes higher than the desired sintering density (80-90% of the theoretical density).On the other hand, above 1800°C, the influence of 02 contained in the sintering atmosphere This is not preferable because the oxidation and evaporation of UD2 will be accelerated.
焼結後、更に還元処理を施す。この還元処理は、Ｈ２等
の還元性雰囲気中で、１０００〜１８００℃、１〜２時
間、熱処理することにより行なわれ得る。After sintering, further reduction treatment is performed. This reduction treatment can be carried out by heat treatment at 1000 to 1800° C. for 1 to 2 hours in a reducing atmosphere such as H2.
この還元処理は、焼結時に雰囲気中の０２の影響で上昇
したペレットの０／Ｕ比（２，１０〜２．２５）を、化
学量論組成（０／Ｕ−２００）まで減少させるために必
要な処理である。This reduction treatment was performed to reduce the 0/U ratio (2.10 to 2.25) of the pellets, which increased due to the influence of 02 in the atmosphere during sintering, to the stoichiometric composition (0/U-200). This is a necessary process.
このようにして得られたペレットのマトリックス密度は
ほぼ理論密度の１００％であり、しかもペレット全体の
密度は、理論密度の８０〜９０％となる。The matrix density of the pellet thus obtained is approximately 100% of the theoretical density, and the density of the entire pellet is 80 to 90% of the theoretical density.
本発明の方法により、低密度化ならびに粒成長促進効果
が得られる理由は必ずしも明らかではないが、次の様に
考えることができる。すなわち、上記雰囲気で焼結を行
なうことにより、焼結速度を律速するウランイオンの活
性化で焼結開始温度が低温域化し、これにより低温度で
成形体に焼結の殻ができる。また、使用する焼結雰囲気
は、ペレットマトリックスへの溶解度が低いため、焼結
が進行して粒成長が進むと、これが粒界に集合し、ボア
を形成する。このボアは粒界を移動するうちに集合合体
し、体積膨張を起こす。このとき、殻のち密さが低けれ
ば集合したボアは、ペレット外部へ逃げるが、ち密さが
高ければ外部へ逃げることが不可能となり、このとき集
合合体による体積膨張の影響を大きく受けて、密度低下
を起こすものと思われる。またウランイオンの活性化に
より、粒界をはさむ相互の結晶粒間のウランイオンのジ
ャンプ頻度が増加し、これによっても粒成長が活発化す
ることになる。The reason why the method of the present invention achieves the effect of lowering density and promoting grain growth is not necessarily clear, but it can be considered as follows. That is, by performing sintering in the above atmosphere, the sintering start temperature is lowered to a lower temperature range due to the activation of uranium ions that determine the sintering rate, thereby forming a sintered shell in the compact at a lower temperature. Furthermore, since the sintering atmosphere used has low solubility in the pellet matrix, as sintering progresses and grain growth progresses, the grains gather at grain boundaries and form bores. As these bores move through the grain boundaries, they aggregate and coalesce, causing volumetric expansion. At this time, if the density of the shell is low, the collected bores will escape to the outside of the pellet, but if the density is high, they will not be able to escape to the outside. It is thought that this will cause a decline. Furthermore, the activation of uranium ions increases the frequency of uranium ion jumps between crystal grains sandwiching grain boundaries, which also activates grain growth.
以下、本発明を実施例により説明するが、本発明はこれ
ら実施例に制限されるものでない。EXAMPLES Hereinafter, the present invention will be explained with reference to Examples, but the present invention is not limited to these Examples.
求塵男
原料粉末（ＵＯ２：）を更に粉砕して、平均粒径０．３
μｍ （ＢＥＴ法による計算値）の混合粉末を調製した
。この粉砕には、ボールミルを使用し、粉砕時間は３０
時間とした。粉砕後、予備成形・造粒を行ない、その後
圧縮成形を行なった。The raw material powder (UO2:) is further crushed to obtain an average particle size of 0.3.
A mixed powder of μm (value calculated by BET method) was prepared. A ball mill was used for this grinding, and the grinding time was 30
It was time. After pulverization, preforming and granulation were performed, and then compression molding was performed.
このときの成形圧力は２ ｔｏｎ／ｃｄであり、６０％
ＴＤの成形体を得た。The molding pressure at this time was 2 ton/cd, which was 60%
A TD molded body was obtained.
次いで、このようにして得た成形体をＣＯ２とＡｒの混
合雰囲気中（ＣＯ２：８０％、Ａｒ：２０％）で焼結し
た。焼結温度は、１７５０℃、時間は４時間であった。Next, the molded body thus obtained was sintered in a mixed atmosphere of CO2 and Ar (CO2: 80%, Ar: 20%). The sintering temperature was 1750°C and the time was 4 hours.
また、処理物の焼結直後におけるＯ／Ｕ比は２．１５で
あった。焼結後還元するためＨ２雰囲気中、１７５０℃
で４時間の還元処理を行なった。Further, the O/U ratio of the treated product immediately after sintering was 2.15. 1750℃ in H2 atmosphere for reduction after sintering
A reduction treatment was performed for 4 hours.
得られたペレットの密度は、８９％ＴＤであり、平均結
晶粒径は４６μｍであった。第２図は、このペレットの
断面の金属組織の顕微鏡写真（４００倍）である。The density of the obtained pellets was 89% TD, and the average crystal grain size was 46 μm. FIG. 2 is a micrograph (400x magnification) of the metal structure of the cross section of this pellet.
比較例
第２図に示すペレットと同程度の密度ペレットを得る為
Ｈ２雰囲気中で製作した例である。ただし、ポア・フォ
ーマーは使用しなかった。以下に製作例を示す。Comparative Example This example was manufactured in an H2 atmosphere to obtain pellets with a density comparable to that of the pellets shown in FIG. However, a pore former was not used. A production example is shown below.
まず原料粉末（ＵＯ２）の圧縮成形を行った。First, the raw material powder (UO2) was compression molded.
このときの成形圧力は２ｔｏｎ／ｃシであり、５０％Ｔ
Ｄの成形体を得た。The molding pressure at this time was 2 tons/c, and 50%T
A molded product D was obtained.
次いで、このようにして得た成形体をＨ２雰囲気中で焼
結した。焼結温度は１６００°Ｃ１時間は４時間であっ
た。The molded body thus obtained was then sintered in an H2 atmosphere. The sintering temperature was 1600°C for 4 hours.
得られたペレットの密度は、９０９６Ｔ Ｄであり、平
均結晶粒径は１８μｍであった。第３図はこのペレット
の断面の金属組織の顕微鏡写真（４００倍）である。The density of the obtained pellets was 9096TD, and the average crystal grain size was 18 μm. FIG. 3 is a micrograph (400x magnification) of the metal structure of the cross section of this pellet.
検討
通常、理論密度の９０％以下のペレットを得る為には、
還元雰囲気下で１６００℃以下での焼結温度で十分であ
った。しかし、このような低温度で焼結したペレットの
焼きしまり値（１７００℃、Ｈ２雰囲気中２４時間処理
）は、理論密度で１％を超える。一方、１６００℃以上
の焼結温度では、ポア・フォーマー添加なしでは９０％
以下の密度を得ることはできなかった。ところが、本発
明に従って得たペレットの焼結密度は１６００℃以上で
焼結したにもかかわらず、９０％以下の密度を何してい
た。このペレットの焼きしまり値は、１％を超えること
はなかった。また得られたペレットの平均結晶粒径は４
０μ以上であり、従来の方法で焼結したペレットの平均
結晶粒径１０〜２０μと比較すると２倍以上であった。Consideration: Normally, in order to obtain pellets with a density of 90% or less of the theoretical density,
A sintering temperature below 1600°C under a reducing atmosphere was sufficient. However, the sintering density value of pellets sintered at such a low temperature (processed at 1700° C. for 24 hours in an H2 atmosphere) exceeds 1% in terms of theoretical density. On the other hand, at a sintering temperature of 1600℃ or higher, 90%
It was not possible to obtain densities below. However, the sintered density of the pellets obtained according to the present invention was 90% or less even though the pellets were sintered at 1600° C. or higher. The compaction value of this pellet never exceeded 1%. The average crystal grain size of the pellets obtained was 4
It was 0μ or more, which was more than twice the average crystal grain size of pellets sintered by the conventional method, which was 10 to 20μ.
第１図は製造工程のフローチャート図、第２図および第
３図は核燃料ペレットの断面の金属組織の顕微鏡写真（
４００倍）である。
出願人代理人 佐 藤 −雄
第１図Figure 1 is a flowchart of the manufacturing process, and Figures 2 and 3 are micrographs of the metal structure of a cross section of nuclear fuel pellets (
400 times). Applicant's agent Mr. Sato Figure 1
Claims (1)
らにその後にこの焼結体を還元雰囲気中で処理すること
により核燃料ペレットを製造するに際し、 前記成形体はポア・フォーマーを含まず、かつ、焼結雰
囲気として、ペレットマトリックスへの溶解度が低くし
かも低温度で焼結が開始するような雰囲気中で焼結を行
なうことを特徴とする、核燃料ペレットの製造方法。 ２、焼結雰囲気が、（イ）ＣＯ＿２および（または）水
蒸気と、（ロ）不活性ガスとの混合ガスからなる、特許
請求の範囲第１項の方法。[Claims] 1. When manufacturing nuclear fuel pellets by molding raw material powder, sintering this molded body, and then treating this sintered body in a reducing atmosphere, the molded body is A method for producing nuclear fuel pellets, characterized by carrying out sintering in an atmosphere that does not contain pore formers and has low solubility in the pellet matrix and starts sintering at a low temperature. . 2. The method according to claim 1, wherein the sintering atmosphere consists of a mixed gas of (a) CO_2 and/or water vapor, and (b) an inert gas.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62082960A JP2620234B2 (en) | 1987-04-06 | 1987-04-06 | Method for producing nuclear fuel pellets |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62082960A JP2620234B2 (en) | 1987-04-06 | 1987-04-06 | Method for producing nuclear fuel pellets |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63249096A true JPS63249096A (en) | 1988-10-17 |
| JP2620234B2 JP2620234B2 (en) | 1997-06-11 |
Family
ID=13788792
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62082960A Expired - Fee Related JP2620234B2 (en) | 1987-04-06 | 1987-04-06 | Method for producing nuclear fuel pellets |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2620234B2 (en) |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5637225A (en) * | 1979-09-03 | 1981-04-10 | Mitsubishi Metal Corp | Dry manufacture of uranium dioxide powder with superior sinterability |
| JPS5648583A (en) * | 1979-09-29 | 1981-05-01 | Tokyo Shibaura Electric Co | Method of making sintered pellet of uranium dioxide |
| JPS5648582A (en) * | 1979-09-29 | 1981-05-01 | Tokyo Shibaura Electric Co | Method of making sintered pellet of uranium dioxide |
-
1987
- 1987-04-06 JP JP62082960A patent/JP2620234B2/en not_active Expired - Fee Related
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5637225A (en) * | 1979-09-03 | 1981-04-10 | Mitsubishi Metal Corp | Dry manufacture of uranium dioxide powder with superior sinterability |
| JPS5648583A (en) * | 1979-09-29 | 1981-05-01 | Tokyo Shibaura Electric Co | Method of making sintered pellet of uranium dioxide |
| JPS5648582A (en) * | 1979-09-29 | 1981-05-01 | Tokyo Shibaura Electric Co | Method of making sintered pellet of uranium dioxide |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2620234B2 (en) | 1997-06-11 |
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