JPS6129678B2 - - Google Patents
Info
- Publication number
- JPS6129678B2 JPS6129678B2 JP56006292A JP629281A JPS6129678B2 JP S6129678 B2 JPS6129678 B2 JP S6129678B2 JP 56006292 A JP56006292 A JP 56006292A JP 629281 A JP629281 A JP 629281A JP S6129678 B2 JPS6129678 B2 JP S6129678B2
- Authority
- JP
- Japan
- Prior art keywords
- sintering
- amount
- sintered
- added
- grain size
- 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
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
- Compositions Of Oxide Ceramics (AREA)
Description
本発明は原子炉燃料用酸化物(UO2およびU,
Puの混合酸化物)のペレツトの焼結法に関す
る。
周知のように通常の原子炉の核燃料としては、
二酸化ウランの焼結ペレツ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
れている。
この場合、該ペレツトは、UO2粉末を(粗成
物)→(造粒)→(潤滑剤の添加)→成形→1600
℃ないし1700℃以上の温度での焼結の工程
(( )に入れた過程は省略されることもある)に
よつてUO2ペレツトに製造されている。
核燃料ペレツトの特性として、好ましい種々の
物理的化学的特性が要求されるが、本発明はこれ
らの特性のうち、核燃料ペレツトの焼結密度およ
び結晶粒径の改善を意図するものである。
UO2ペレツトの焼結密度は通常理論値のおよそ
95%が要求され、かつこの焼結密度において熱的
に安定であることが要求される。ここで熱的に安
定であるとは、1つの目安として焼結されたペレ
ツトを1700℃で24時間再焼結する時の緻密度化
(焼しまり)の程度が小さいことであり、通常2
%以下、好ましくは1%以下であることが望まれ
る。
この熱的に安定な95%の焼結密度を達成するた
めに少くとも1600℃以上、通常1700℃以上の温度
で焼結する必要があつた。このように1600℃ない
し1700℃以上の高温を要することはそれ自体、高
価な設備を必要とし、エネルギーコストも高く、
また耐火物を使用している炉においては、耐火物
の消耗が激しくその補修による損失(補修費、設
備稼動率)が多くその改善によるメリツトは大き
く、仮にこの焼結温度が100℃低下されても、経
済的効率は増大する。
従来UO2の焼結密度の向上と焼結温度の低下の
ために、種々の研究が行なわれてきており、例え
ば原料とするUO2粉末の活性化、焼結雰囲気の改
善、添加物による効果等の確認が行なわれてきた
が、結果的には、現段階ではこれらのいづれの方
法もその効果が小さいということで工業的に利用
されるに至つてない。また先に述べた熱的に安定
なペレツトが要求されるに至つては、焼結温度を
1700℃以上にすることが工業的に通常行なわれて
おり、低温で焼結することにより熱的に安定な90
%の焼結密度を有するペレツトの製造に関する試
みはほとんどない。
核燃料ペレツトに要求される特性として、先に
述べた熱的に安定な焼結密度以外に、最近核分裂
生成物による燃料被覆管の応力腐食割れを低減化
するために、核分裂生成物の保留能が大きなペレ
ツトが望まれている。この目的のために結晶粒を
焼結中に成長させ粗大化させることが試みられ、
そのためにUO2にNb化合物を添加して焼結する
研究が行なわれている。
このような状況のもとに本発明者等はUO2の焼
結に際して、種々の金属化合物の微量を添加する
こと試みたが、微量のLi化合物を添加しておく
と、従来よりも低い温度で焼結が進み、結晶粒度
が粗大化することを見出した。このことは、従来
よりも低い温度で高密度かつ結晶粒粗大なペレツ
トを得ることができ、その効果は製造技術上重要
である。また、微量のLi化合物を添加した粉末を
従来1600℃または1700℃以上の温度で焼結するこ
とにより、結晶粒は著しく粗大化し、その核分裂
生成物の保留能が大きくなることが期待される。
即ち、本発明によれば、UO2粉末にLi2Oまた
は加熱によつてLi2Oを生成する化合物の粉末を
Li2Oとして0.005%〜1.0重量%を混じて既知の方
法で圧粉体となし、これを非酸化性雰囲気中で焼
結することからなるUO2核燃料ペレツトの製法が
提供される。
本発明において使用される核燃料酸化物は主と
してUO2であるが、前述のように、MOXとよば
れるPuとの混合酸化物であつてもよく、そのこ
とは理論的に当業者によつて認められよう。
UO2粉末は化学量論的関係からずれていてもよ
いが、ずれている必要もなく、通常の方法によつ
て得られるものでよい。
添加するLi化合物はLi2O,LiOH,Li2CO3,
LiNO3Liのハロゲン化物等のLiを含有しているも
のなら何でも使用できる。安価で好ましいものは
Li2O,LiOH等であり、その添加量はUO2に対し
てLi2Oとして0.005〜1.0重量%である。0.005%
未満では本発明の目的を達成し難く、1.0%以上
加えてもその添加の効果は飽和し、ペレツト中に
残存するLi濃度が高くなり核燃料として好ましく
ない結果をもたらすことが予想される。
本発明において、焼結する雰囲気は通常H2ガ
スであるが、他にH2/N2混合ガスまたは真空雰
囲気であつてもその効果に特に顕著な差はなく、
いずれの雰囲気においても良好な結果が得られ
る。
圧粉体(グリーンペレツト)の成形条件に特に
制限はなく、Liを添加混合した二酸化ウラン粉末
を金型に充填し、所定の圧力で成形する方法であ
る。
焼結温度に関しては、すでに述べたように工業
的には少くとも1600℃以上、通常1700℃以上であ
る。本発明の方法において、特定の焼結密度を達
成するための焼結温度は、Liの添加量によつて異
なり、Liの添加量を増すほどその温度は低下す
る。また焼結体(焼結ペレツト)に観察される結
晶粒径も焼結密度と同様、特定の粒度を得るため
の焼結温度はLiの添加量によつて異なり、Liの添
加量を増すほどその温度は低下する。しかしなが
ら、焼結密度および結晶粒度への効果におよぼす
Li添加量の影響は、添加量の少ない時に顕著であ
り添加量が多くなるにつれて飽和する傾向にあ
る。
本発明において、このようにLiを二酸化ウラン
粉末に添加することにより、従来よりも低い温度
で焼結密度を高めることが出来、同時に結晶粒度
の粗大化が得られるが、一方Liの添加量を増すこ
とおよび焼結温度を低下することは、結果的に焼
結体中に残存するLi含有量が多くなる。UO2焼結
体中に残存するLi量が多くなることは、単に不純
物量の増加という観点から、定性的には好ましく
なく、定量的数値制限が設定し得ない現段階にお
いては、なるべく残存Li量は少ないことが好まし
い。
なお、焼結時間については特に制限はなく、経
験的または実験的に容易に定めることができる。
通常の温度条件下では約2時間程度である。
次に図面を参照して、本発明を具体的に説明す
る。以下の記載において%はすべて重量%であ
る。
第1図は平均粒径約1μ(沈降法による)の
UO2粉末に、潤滑剤として0.2%のステアリン酸
亜鉛を添加し、さらにそれぞれ、0%、0.01%、
0.05%、0.1%のLi2Oを添加したものを、金型を
用いて3t/cm2の圧力で直径10mm、高さ15mmの圧粉
体(グリーンペレツト)としたもの(重さ約7
g)を、水素気流中で種々の温度で焼結したUO2
ペレツトの焼結温度と焼結密度の関係を示す。第
2図は上記のUO2の焼結温度と平均結晶粒径の関
係を示す。
なお、Li2Oの添加量と焼結温度、焼結ペレツ
ト中のLi2O残存量の関係は次の表と第3図にま
とめて示す。
The present invention uses oxides for nuclear reactor fuel (UO 2 and U,
This paper relates to a method for sintering pellets of Pu (mixed oxide of Pu). As is well known, nuclear fuel for normal nuclear reactors is
Sintered uranium dioxide pellets filled in a Zircaloy or other cladding tube are used as nuclear fuel elements. In this case, the pellets are made by mixing UO2 powder (crude product) → (granulation) → (addition of lubricant) → molding → 1600
It is manufactured into UO2 pellets by a sintering process (steps in parentheses may be omitted) at temperatures between 1700°C and above. Nuclear fuel pellets are required to have various desirable physical and chemical properties, and among these properties, the present invention is intended to improve the sintered density and grain size of nuclear fuel pellets. The sintered density of UO 2 pellets is usually around the theoretical value.
95% and is required to be thermally stable at this sintered density. Here, thermal stability means that the degree of densification (sintering compaction) when re-sintering the sintered pellets at 1700℃ for 24 hours is small, and usually 2.
% or less, preferably 1% or less. In order to achieve this thermally stable 95% sintered density, it was necessary to sinter at a temperature of at least 1600°C or higher, usually 1700°C or higher. Requiring high temperatures of 1600℃ to 1700℃ or higher in this way requires expensive equipment and high energy costs.
In addition, in furnaces that use refractories, the refractories are rapidly worn out and there is a lot of loss (repair costs, equipment operating rate) due to their repair. Also, economic efficiency increases. Conventionally, various studies have been conducted to improve the sintered density of UO 2 and lower the sintering temperature, such as activating the UO 2 powder used as a raw material, improving the sintering atmosphere, and investigating the effects of additives. However, as a result, none of these methods have been used industrially at this stage because their effects are small. In addition, when thermally stable pellets are required as mentioned above, the sintering temperature must be adjusted.
Sintering at a temperature of 1,700°C or higher is usually carried out industrially, and sintering at a low temperature results in thermally stable 90°C.
There have been few attempts to produce pellets with a sintered density of . In addition to the above-mentioned thermally stable sintered density, properties required for nuclear fuel pellets include the ability to retain fission products in order to reduce stress corrosion cracking of the fuel cladding caused by fission products. Large pellets are desired. For this purpose, attempts have been made to grow and coarsen crystal grains during sintering.
For this purpose, research is being conducted on adding Nb compounds to UO 2 and sintering it. Under these circumstances, the inventors of the present invention attempted to add trace amounts of various metal compounds when sintering UO 2 , but adding a trace amount of Li compounds resulted in a lower temperature than before. It was found that sintering progresses and the grain size becomes coarser. This makes it possible to obtain pellets with high density and coarse grains at a lower temperature than before, and this effect is important in terms of manufacturing technology. Furthermore, by conventionally sintering powder to which a small amount of Li compound has been added at a temperature of 1,600°C or 1,700°C or higher, the crystal grains become significantly coarser, and the ability to retain fission products is expected to increase. That is, according to the present invention, Li 2 O or a powder of a compound that generates Li 2 O upon heating is added to the UO 2 powder.
A method for producing UO 2 nuclear fuel pellets is provided, which comprises mixing 0.005% to 1.0% by weight of Li 2 O into a green compact by a known method and sintering the green compact in a non-oxidizing atmosphere. The nuclear fuel oxide used in the present invention is mainly UO2 , but as mentioned above, it may also be a mixed oxide with Pu called MOX, which is theoretically recognized by those skilled in the art. Let's be. Although the UO 2 powder may deviate from the stoichiometric relationship, it is not necessary to deviate from the stoichiometric relationship and may be obtained by a conventional method. The Li compounds added are Li 2 O, LiOH, Li 2 CO 3 ,
Anything containing Li, such as a halide of LiNO 3 Li, can be used. Cheap and preferable
Li 2 O, LiOH, etc., and the amount added is 0.005 to 1.0% by weight as Li 2 O based on UO 2 . 0.005%
If it is less than 1.0%, it will be difficult to achieve the purpose of the present invention, and even if it is added in an amount of 1.0% or more, the effect of addition will be saturated, and it is expected that the concentration of Li remaining in the pellet will increase, resulting in unfavorable results as a nuclear fuel. In the present invention, the sintering atmosphere is usually H 2 gas, but there is no noticeable difference in the effect even if it is an H 2 /N 2 mixed gas or a vacuum atmosphere.
Good results can be obtained in any atmosphere. There are no particular restrictions on the molding conditions for the compact (green pellet), and the method is to fill a mold with uranium dioxide powder mixed with Li and mold it under a predetermined pressure. Regarding the sintering temperature, as already mentioned, industrially it is at least 1600°C or higher, usually 1700°C or higher. In the method of the present invention, the sintering temperature for achieving a specific sintered density varies depending on the amount of Li added, and the temperature decreases as the amount of Li added increases. In addition, the crystal grain size observed in the sintered body (sintered pellet) is similar to the sintered density, and the sintering temperature to obtain a specific grain size varies depending on the amount of Li added. Its temperature decreases. However, the effect on sintered density and grain size
The influence of the amount of Li added is noticeable when the amount added is small, and tends to become saturated as the amount added increases. In the present invention, by adding Li to uranium dioxide powder in this way, it is possible to increase the sintered density at a lower temperature than before, and at the same time coarsen the grain size. Increasing the Li content and lowering the sintering temperature result in an increase in the Li content remaining in the sintered body. An increase in the amount of Li remaining in the UO 2 sintered body is qualitatively unfavorable from the viewpoint of simply increasing the amount of impurities, and at this stage, where quantitative numerical limits cannot be set, it is necessary to reduce the amount of remaining Li as much as possible. Preferably, the amount is small. Note that the sintering time is not particularly limited and can be easily determined empirically or experimentally.
Under normal temperature conditions, it takes about 2 hours. Next, the present invention will be specifically described with reference to the drawings. In the following description, all percentages are by weight. Figure 1 shows an average particle size of approximately 1μ (according to the sedimentation method).
To the UO 2 powder, 0.2% zinc stearate was added as a lubricant, and further 0%, 0.01%,
The powder containing 0.05% and 0.1% Li 2 O was made into green pellets (green pellets) with a diameter of 10 mm and a height of 15 mm using a mold at a pressure of 3 t/cm 2 (weighing approximately 7 mm).
UO 2 g) sintered at various temperatures in a hydrogen stream
The relationship between pellet sintering temperature and sintered density is shown. FIG. 2 shows the relationship between the sintering temperature and average grain size of the above UO 2 . The relationship between the amount of Li 2 O added, the sintering temperature, and the amount of Li 2 O remaining in the sintered pellets is summarized in the following table and FIG. 3.
【表】
第1図から明らかなように、Li2Oの添加量が
増すにしたがつて焼結密度は増加するが、その増
加割合は比較的低い焼結温度の時に顕著であり、
例えば1150℃での焼結において、0.05%Li2Oの添
加により焼結密度は63%から91%まで高めること
が出来、その焼結促進に与えるLi2Oの効果はき
わめて優れている。しかしながら、Li2Oの添加
量を0.05%から0.1%および0.2%に増加しても焼
結密度はそれぞれ91%、93%、93.5%となり、
Li2Oの添加によるその促進効果は約0.1%付近で
飽和することが確認される。(Li2O0.2%の場合は
第1図に示されていない。)
第2図に示したように、焼結ペレツトに観察さ
れる平均結晶粒径は、いづれの焼結温度において
も、Li2Oの添加により粗大化し、その粗大化の
割合は、焼結温度が高い時に顕著である。例えば
1650℃での焼結において0.05%のLi2Oを添加する
ことにより、平均結晶粒径は約120μmとなり
Li2Oを添加しなかつた時の11μmと較べて約10
倍の増加を示す。なおLi2Oの添加量を0.05%から
0.1%に増加しても平均結晶粒径は120μmから
135μm程度と比較的小さな増加しか示さず、
Li2Oの添加による結晶粒粗大化の傾向は0.1%付
近で飽和していると云える。
図3および表1に示したようにUO2焼結体中に
残存するLi量は、Li2Oの添加量が多いほど、ま
た焼結温度が低いほど増加する。先に述べたよう
にLi残存量は少ないほど好ましいということが出
来、この点からもLi2Oの添加により期待される
効果として、焼結密度の促進、結晶粒の粗大化ま
たはこれらの両方を選択することによりLi2Oの
添加量および焼結温度を選択すべきである。
これらの図に示された結果から判断すれば、Li
化合物の添加量はLi2Oとして0.005%程度であつ
ても有意であるといえる。
これらの図から明らかなように、Li2Oを0.05%
添加した時、1350℃で理論値に対する94%の焼結
密度と約40μmの平均結晶粒径が得られ、その時
のLi残存量は70ppmである。もし1650℃焼結す
れば平均結晶粒径は120μmに達し、Li残存量は
30ppmである。
Li2Oを0.1%添加した時は1350℃で理論値に対
する95.5%の焼結密度と約45μmの平均結晶粒径
が得られ、その時のLi残存量は160ppmである。
もし1650℃で焼結すれば、平均結晶粒径は135μ
mに達し、Li残存量は45ppmである。
次に条件を変えて行つた実施例を示す。
実施例 1
平均粒径約1μmのUO2粉末に、潤滑剤として
0.2%のステアリン酸亜鉛を添加し、さらに0.01
%のLi2Oを添加したものを、金型を用いて3t/cm2
の圧力で直径10mm、高さ15mmの圧粉体としたもの
を水素気流中1650℃で2時間焼結した。得られた
UO2ペレツトの焼結密度は95.1%、平均結晶粒径
は約70μmであり、残存Li含有量は15ppmであ
つた。Li2Oを添加しない時の焼結密度および平
均結晶粒径はそれぞれ94.5%、20μmであつた。
実施例 2
Li2Oの代りにLiOHを0.1%用い、後は前記の条
件で1350℃と1650℃で焼結を行なつた。1350℃で
焼結したものは焼結密度94%、平均結晶粒径35μ
m、残存Li量95ppmであつた。1650℃で焼結し
たものは焼結密度96%、平均結晶粒径105μm、
Li残存量25ppmであつた。
実施例 3
Li2Oの代りにLiFを0.1%用い、後は前記の条
件で、1350℃と1650℃で焼結を行なつた。1350℃
で焼結したものは焼結密度94%、平均結晶粒径40
μm、残存Li量80ppmであつた。1650℃で焼結
したものは焼結密度96%、平均結晶粒径100μ
m、Li残存量20ppmであつた。
実施例 4
Li2Oの代りに酢酸リチウムを0.2%用い、後は
前記の条件で、1350℃と1650℃で焼結を行つた。
1350℃で焼結したものは焼結密度92.5%、平均結
晶粒径25μm、残存Li量60ppmであつた。1650
℃で焼結したものは焼結密度95%、平均結晶粒径
75μm、Li残存量10ppmであつた。
以上記したように、本発明によれば微量のLi化
合物の添加によつて、焼結温度の低下、焼結密度
の上昇、平均結晶粒径の増大の3種の利益を一拳
に達成することができ、本発明の効果は極めて大
であるといえる。[Table] As is clear from Figure 1, the sintered density increases as the amount of Li 2 O added increases, but the rate of increase is remarkable at relatively low sintering temperatures.
For example, in sintering at 1150°C, the sintered density can be increased from 63% to 91% by adding 0.05% Li 2 O, and the effect of Li 2 O on promoting sintering is extremely excellent. However, even if the amount of Li 2 O added was increased from 0.05% to 0.1% and 0.2%, the sintered density remained 91%, 93%, and 93.5%, respectively.
It is confirmed that the promoting effect of adding Li 2 O is saturated at around 0.1%. (The case of 0.2% Li 2 O is not shown in Figure 1.) As shown in Figure 2, the average grain size observed in the sintered pellets is The addition of Li 2 O causes coarsening, and the rate of coarsening is remarkable when the sintering temperature is high. for example
By adding 0.05% Li 2 O during sintering at 1650℃, the average grain size becomes approximately 120μm.
Approximately 10μm compared to 11μm without adding Li 2 O
Showing a fold increase. Note that the amount of Li 2 O added starts from 0.05%.
Even if it increases to 0.1%, the average grain size will still be 120 μm.
It showed only a relatively small increase of about 135 μm,
It can be said that the tendency of crystal grain coarsening due to the addition of Li 2 O is saturated at around 0.1%. As shown in FIG. 3 and Table 1, the amount of Li remaining in the UO 2 sintered body increases as the amount of Li 2 O added increases and as the sintering temperature decreases. As mentioned earlier, it can be said that the smaller the residual amount of Li, the better. From this point of view, the expected effects of adding Li 2 O are to promote sintered density, coarsen grains, or both. The amount of Li 2 O added and the sintering temperature should be selected accordingly. Judging from the results shown in these figures, Li
It can be said that even if the amount of the compound added is about 0.005% as Li 2 O, it is significant. As is clear from these figures, Li 2 O at 0.05%
When added, a sintered density of 94% of the theoretical value and an average crystal grain size of about 40 μm were obtained at 1350° C., and the residual amount of Li at that time was 70 ppm. If sintered at 1650℃, the average grain size will reach 120μm, and the remaining amount of Li will be
It is 30ppm. When 0.1% Li 2 O was added, a sintered density of 95.5% of the theoretical value and an average crystal grain size of about 45 μm were obtained at 1350° C., and the remaining amount of Li at that time was 160 ppm.
If sintered at 1650℃, the average grain size is 135μ
m, and the remaining amount of Li is 45 ppm. Next, examples will be shown in which the conditions were changed. Example 1 UO 2 powder with an average particle size of about 1 μm was added as a lubricant.
Added 0.2% zinc stearate and further 0.01
% of Li 2 O was added to 3t/cm 2 using a mold.
A green compact with a diameter of 10 mm and a height of 15 mm was sintered at 1,650°C in a hydrogen stream for 2 hours at a pressure of . obtained
The sintered density of the UO 2 pellets was 95.1%, the average grain size was about 70 μm, and the residual Li content was 15 ppm. The sintered density and average grain size when Li 2 O was not added were 94.5% and 20 μm, respectively. Example 2 LiOH was used at 0.1% instead of Li 2 O, and sintering was carried out at 1350° C. and 1650° C. under the above conditions. Those sintered at 1350℃ have a sintered density of 94% and an average grain size of 35μ.
m, and the residual Li amount was 95 ppm. Those sintered at 1650℃ have a sintered density of 96%, an average grain size of 105μm,
The remaining amount of Li was 25 ppm. Example 3 LiF was used at 0.1% instead of Li 2 O, and sintering was carried out at 1350°C and 1650°C under the above conditions. 1350℃
The sintered one has a sintered density of 94% and an average grain size of 40
μm, and the residual Li amount was 80 ppm. Those sintered at 1650℃ have a sintered density of 96% and an average grain size of 100μ.
m, and the residual amount of Li was 20 ppm. Example 4 Using 0.2% lithium acetate instead of Li 2 O, sintering was carried out at 1350°C and 1650°C under the above conditions.
The material sintered at 1350°C had a sintered density of 92.5%, an average grain size of 25 μm, and a residual Li content of 60 ppm. 1650
Those sintered at °C have a sintered density of 95% and an average grain size.
The diameter was 75 μm, and the residual amount of Li was 10 ppm. As described above, according to the present invention, the three benefits of lowering the sintering temperature, increasing the sintered density, and increasing the average grain size can be achieved by adding a small amount of Li compound. Therefore, it can be said that the effects of the present invention are extremely large.
第1図はUO2粉末にLi2Oを添加して焼結する
際の焼結温度と焼結密度の関係を示す。第2図は
第1図と同じ場合の焼結温度と平均結晶粒径の関
係を示す。第3図は第1図および第2図と同じ場
合の焼結温度と残存Liの量の関係を示す。
Figure 1 shows the relationship between sintering temperature and sintered density when Li 2 O is added to UO 2 powder and sintered. FIG. 2 shows the relationship between sintering temperature and average grain size in the same case as FIG. 1. FIG. 3 shows the relationship between the sintering temperature and the amount of residual Li in the same case as FIGS. 1 and 2.
Claims (1)
生成する化合物の粉末をLi2Oとして0.005%〜1.0
重量%を混じて既知の方法で圧粉体となし、これ
を非酸化性雰囲気中で焼結することからなるUO2
核燃料ペレツトの製法。 2 特許請求の範囲第1項記載の方法であつて、
1350℃以上の温度で焼結することを特徴とする方
法。 3 特許請求の範囲第2項記載の方法であつて、
Li2Oを生成する化合物の粉末を0.1重量%以上混
ずることを特徴とする方法。[Claims] 1 UO 2 powder with Li 2 O or powder of a compound that generates Li 2 O by heating as Li 2 O from 0.005% to 1.0
UO 2 consisting of mixing % by weight to form a green compact by a known method and sintering this in a non-oxidizing atmosphere.
Method for producing nuclear fuel pellets. 2. The method according to claim 1, comprising:
A method characterized by sintering at a temperature of 1350°C or higher. 3. The method according to claim 2, comprising:
A method characterized by mixing 0.1% by weight or more of a powder of a compound that generates Li 2 O.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56006292A JPS57197496A (en) | 1981-01-21 | 1981-01-21 | Method of making nuclear fuel pellet |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56006292A JPS57197496A (en) | 1981-01-21 | 1981-01-21 | Method of making nuclear fuel pellet |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57197496A JPS57197496A (en) | 1982-12-03 |
| JPS6129678B2 true JPS6129678B2 (en) | 1986-07-08 |
Family
ID=11634300
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56006292A Granted JPS57197496A (en) | 1981-01-21 | 1981-01-21 | Method of making nuclear fuel pellet |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57197496A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61116685A (en) * | 1984-11-10 | 1986-06-04 | 原子燃料工業株式会社 | Nuclear fuel pellet |
| US4869866A (en) * | 1987-11-20 | 1989-09-26 | General Electric Company | Nuclear fuel |
| US4869868A (en) * | 1987-11-23 | 1989-09-26 | General Electric Company | Nuclear fuel |
-
1981
- 1981-01-21 JP JP56006292A patent/JPS57197496A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57197496A (en) | 1982-12-03 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US6251310B1 (en) | Method of manufacturing a nuclear fuel pellet by recycling an irradiated oxide fuel pellet | |
| US5882552A (en) | Method for recycling fuel scrap into manufacture of nuclear fuel pellets | |
| US6251309B1 (en) | Method of manufacturing large-grained uranium dioxide fuel pellets containing U3O8 | |
| EP0502395B1 (en) | Nuclear fuel pellets and method of manufacturing the same | |
| JPS62232595A (en) | Nuclear fuel sintered body and manufacture thereof | |
| US5978431A (en) | Nuclear fuel pellets | |
| CN1133176C (en) | Method for preparing Gd2O3-UO2 flammable poison fuel core block by using U3O8 powder | |
| JPS6129678B2 (en) | ||
| JPS5948686A (en) | Method of making low density oxide fuel pellet | |
| US3167388A (en) | Massive crystals of uo | |
| KR100331483B1 (en) | Method of manufacturing oxide fuel pellets containing neutron-absorbing materials | |
| KR100272727B1 (en) | Method of manufacturing uranium dioxide fuel pellet consisting of duplex grains | |
| US3320034A (en) | Conversion of uo to uc | |
| US3272600A (en) | Method of producing nuclear fuel monocarbides from higher carbides | |
| JPH01248092A (en) | Manufacture of nuclear fuel pellet | |
| US3037839A (en) | Preparation of uo for nuclear reactor fuel pellets | |
| KR920000286B1 (en) | Manufacturing method of oxidized fuel sintered body | |
| JPH0731265B2 (en) | Manufacturing method of nuclear fuel pellets | |
| JP2662359B2 (en) | Method for producing nuclear fuel pellets | |
| JP2907694B2 (en) | Method for producing nuclear fuel pellets | |
| JPH0470594A (en) | Fabrication of nuclear fuel pellet of oxide with niobia additive | |
| JPS6236589A (en) | Manufacture of nuclear-fuel sintered body containing gadolinium oxide | |
| US3369890A (en) | Method for making niobium-uranium alloy with predetermined total void volume and void size | |
| JPS6130235B2 (en) | ||
| JPH0755975A (en) | Manufacturing method of nuclear fuel pellets |