JPH0761820A - Production of nuclear fuel pellet - Google Patents
Production of nuclear fuel pelletInfo
- Publication number
- JPH0761820A JPH0761820A JP5206768A JP20676893A JPH0761820A JP H0761820 A JPH0761820 A JP H0761820A JP 5206768 A JP5206768 A JP 5206768A JP 20676893 A JP20676893 A JP 20676893A JP H0761820 A JPH0761820 A JP H0761820A
- Authority
- JP
- Japan
- Prior art keywords
- pellets
- nuclear fuel
- powder
- ratio
- sintering
- 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.)
- Withdrawn
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
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、活性度の大きなＵＯ2
粉末から結晶粒径の大きな核燃料ペレットを製造する方
法に関する。更に詳しくは、照射時における核分裂生成
ガスの保持性能に優れたＵＯ2核燃料ペレットの製造方
法に関するものである。BACKGROUND OF THE INVENTION The present invention relates to UO 2 having high activity.
The present invention relates to a method for producing a nuclear fuel pellet having a large crystal grain size from a powder. More specifically, the present invention relates to a method for producing UO 2 nuclear fuel pellets having excellent retention performance of fission product gas during irradiation.
【０００２】[0002]
【従来の技術】近年、原子力発電における技術革新の試
みのひとつとして、原子炉燃料をより長期間使用する、
いわゆる高燃焼度化の計画が検討されている。この高燃
焼度化に伴って燃料からの核分裂生成ガス（ＦＰガス）
の放出が増大し、これによる燃料棒内の内圧上昇及びペ
レット−被覆管ギャップの熱伝導度の低下が起こり、燃
料の健全性が低下する可能性があるため、高燃焼度化を
実現するにはＦＰガスのペレット外への放出を低減する
ことが必要である。2. Description of the Related Art In recent years, as one of the attempts of technological innovation in nuclear power generation, the use of nuclear reactor fuel for a longer period,
A so-called high burnup plan is being considered. The fission product gas (FP gas) from the fuel accompanying this higher burnup
Emission increases, which causes an increase in internal pressure in the fuel rod and a decrease in the thermal conductivity of the pellet-cladding gap, which may reduce the fuel integrity. It is necessary to reduce the emission of FP gas outside the pellet.
【０００３】このＦＰガスの保持効果を高めるために
は、ペレットの結晶粒径を大きくするのが有効であるこ
とが判っている。本出願人は重ウラン酸アンモニウム
（ＡＤＵ）の生成条件をコントロールすることにより、
ＵＯ2粉末から結晶粒径が２０μｍ 以上の大きなＵＯ2
ペレットを製造する方法を提案してきた（例えば、特開
昭６ ２−２９７２１５）。It has been found that increasing the crystal grain size of the pellet is effective for enhancing the effect of retaining the FP gas. By controlling the conditions for the production of ammonium diuranate (ADU), the applicant has
UO 2 grain size from the powder is not less than 20μm large UO 2
A method for producing pellets has been proposed (for example, JP-A-6-297215).
【０００４】[0004]
【発明が解決しようとする課題】しかし、上記方法で用
いる高活性粉末の取扱い及び成形を大気下で行い、この
高活性粉末の成形体を通常の条件で焼結すると、焼結し
た後のペレットに割れ、欠けを生じる不具合があった。
この理由は次のように考えられる。即ち、製造された初
期の高活性のＵＯ2粉末はＯ／Ｕ比（ウランに対する酸
素の原子比）が２．００に近い状態であるが、粉末での
保管及びペレットへの成形を大気下で行うと、保管中の
粉末及び成形中のペレットが大気中の酸素により徐々に
酸化されＯ／Ｕ比が次第に大きくなっていく。そして酸
化が進行してＯ／Ｕ比が２．２５付近になると、結晶構
造はＵＯ2相から高次の酸化物であるＵ4Ｏ9相に変化
し、更に酸化が進行するとＵ3Ｏ7相に変化していく。こ
のような高次の酸化物になった成形体をそのまま通常の
焼結雰囲気である水素中で特に注意を払うことなく高温
に加熱して焼結すると、焼結時にＵ4Ｏ9或いはＵ3Ｏ7か
らＵＯ2への相の変化が生じることにより、焼結後のペ
レットには割れ、欠けが入る確率が極めて高くなる。However, when the high activity powder used in the above method is handled and molded in the atmosphere and the compact of this high activity powder is sintered under normal conditions, the pellets after sintering are formed. There was a problem of cracking and chipping.
The reason for this is considered as follows. That is, the initially produced highly active UO 2 powder had an O / U ratio (atomic ratio of oxygen to uranium) close to 2.00, but was stored in powder and molded into pellets under air. When this is done, the powder being stored and the pellets being molded are gradually oxidized by oxygen in the atmosphere, and the O / U ratio gradually increases. Then, when the oxidation progresses and the O / U ratio approaches 2.25, the crystal structure changes from the UO 2 phase to the U 4 O 9 phase which is a higher-order oxide, and when the oxidation further proceeds, U 3 O 7 Change into phases. When such a high-order oxide formed body is heated as it is in a normal sintering atmosphere of hydrogen without being particularly careful to be heated to a high temperature and sintered, U 4 O 9 or U 3 is produced at the time of sintering. Due to the change of the phase from O 7 to UO 2 , the probability of cracks and chips in the pellets after sintering becomes extremely high.
【０００５】本発明の目的は、高活性度のＵＯ2粉末か
ら結晶粒径の大きなＵＯ2ペレットを割れや欠けのない
状態で製造する方法を提供することにある。An object of the present invention is to provide a method for producing UO 2 pellets having a large crystal grain size from a highly active UO 2 powder without cracking or chipping.
【０００６】[0006]
【課題を解決するための手段】本発明は、活性度の大き
なＵＯ2粉末を成形し、この成形体を焼結して結晶粒径
の大きなＵＯ2ペレットを製造する核燃料ペレットの製
造方法の改良である。その特徴ある構成は、前記成形体
を５００〜１０００℃の温度範囲で加熱還元することに
よりＯ／Ｕ比を２．２５以下に調節する第１工程と、前
記還元した成形体を１２００〜１８００℃の温度範囲の
還元雰囲気中で焼結することによりＯ／Ｕ比が２．００
の焼結ペレットを得る第２工程とを含むことにある。DISCLOSURE OF THE INVENTION The present invention provides an improved method for producing nuclear fuel pellets, in which UO 2 powder having a high activity is molded and the compact is sintered to produce UO 2 pellets having a large crystal grain size. Is. The characteristic constitution is that the first step of adjusting the O / U ratio to 2.25 or less by heating and reducing the molded body in the temperature range of 500 to 1000 ° C., and the reduced molded body of 1200 to 1800 ° C. O / U ratio is 2.00 by sintering in a reducing atmosphere in the temperature range of
And a second step of obtaining a sintered pellet of 1.
【０００７】なお、焼結密度をコントロールするため
に、成形は原料ＵＯ2粉末に６００℃以下の温度で分解
し揮発する平均粒径が５〜３００μｍの気孔形成剤を
０．３〜１．４重量％均一に添加した後で行うことが好
ましい。In order to control the sintered density, the raw material UO 2 powder is decomposed at a temperature of 600 ° C. or less and volatilized with 0.3 to 1.4 of a pore-forming agent having an average particle diameter of 5 to 300 μm. It is preferable to carry out after the addition is made uniformly by weight.
【０００８】第１工程において、ＵＯ2粉末の成形体を
５００〜１０００℃の温度範囲でかつ還元雰囲気中で加
熱することによりＯ／Ｕ比を２．２５以下に調節する。
この還元加熱処理は焼結が顕著に起こる前に存在する相
をＵＯ2の状態にするために行う。加熱温度が５００℃
未満では還元速度が非常に遅いため比較的短時間に還元
を終了させることができず、一方１０００℃を超えると
焼結が顕著になるのでそれぞれ好ましくない。Ｏ／Ｕ比
を２．２５以下とするための還元雰囲気としては、水素
とスチームの混合ガス又は一酸化炭素と二酸化炭素の混
合ガスなどを利用することが可能であり、いずれの混合
ガスを使用する場合も２種類のガスの混合比をコントロ
ールすることにより理論的に酸素ポテンシャルを−２１
０ｋＪ／ｍｏｌ以下とすることが好ましい。In the first step, the O / U ratio is adjusted to 2.25 or less by heating the UO 2 powder compact in a temperature range of 500 to 1000 ° C. and in a reducing atmosphere.
This reduction heat treatment is performed in order to bring the existing phase into UO 2 state before significant sintering occurs. Heating temperature is 500 ℃
If it is less than 1, the reduction rate is very slow and the reduction cannot be completed in a relatively short time. On the other hand, if it exceeds 1000 ° C., the sintering becomes remarkable, which is not preferable. As the reducing atmosphere for setting the O / U ratio to 2.25 or less, a mixed gas of hydrogen and steam, a mixed gas of carbon monoxide and carbon dioxide, or the like can be used, and any mixed gas can be used. In this case, the oxygen potential can be theoretically -21 by controlling the mixing ratio of the two gases.
It is preferably 0 kJ / mol or less.
【０００９】また第２工程において、還元雰囲気中で１
２００〜１８００℃の高温で焼結することにより緻密化
を終了させると同時に焼結体のＯ／Ｕ比を製品としての
ペレットの規格値として通常要求される２．００に調節
する。１２００℃未満では緻密化が不十分になり、一方
１８００℃を超えると工業的な加熱システムでは実現困
難となりかつエネルギ消費が甚大となり、好ましくな
い。Ｏ／Ｕ比を２．００に調節するためには理論的に雰
囲気の酸素ポテンシャルを−３４０ｋＪ／ｍｏｌ以下と
することが好ましい。このような酸素ポテンシャルの雰
囲気は第１工程での加熱と同様に水素とスチームの混合
ガス又は一酸化炭素と二酸化炭素の混合ガスなどを利用
することにより、２種類のガスの混合比をコントロール
して得られる。In the second step, 1 in the reducing atmosphere
The densification is completed by sintering at a high temperature of 200 to 1800 ° C., and at the same time, the O / U ratio of the sintered body is adjusted to 2.00 which is usually required as a standard value of pellets as a product. If the temperature is lower than 1200 ° C, the densification becomes insufficient, while if it exceeds 1800 ° C, it becomes difficult to realize with an industrial heating system and energy consumption becomes enormous, which is not preferable. In order to adjust the O / U ratio to 2.00, it is theoretically preferable that the oxygen potential of the atmosphere is −340 kJ / mol or less. The atmosphere of such oxygen potential controls the mixing ratio of the two kinds of gas by using a mixed gas of hydrogen and steam or a mixed gas of carbon monoxide and carbon dioxide as in the heating in the first step. Obtained.
【００１０】[0010]
【作用】第１工程において、ＵＯ2粉末の成形体を還元
雰囲気中で５００〜１０００℃の温度で加熱することに
より、第２工程の焼結が顕著に起こる前に存在する相を
ＵＯ2相にして、Ｏ／Ｕ比を２．２５以下に調節する。
また第２工程において、還元雰囲気中で１２００〜１８
００℃の高温で焼結することにより、第１工程で加熱し
た成形体をＵＯ2相のままの状態で緻密化し、ペレット
のＯ／Ｕ比を２．００に調節する。In the first step, the UO 2 powder compact is heated at a temperature of 500 to 1000 ° C. in a reducing atmosphere so that the UO 2 phase existing before the significant sintering in the second step occurs. Then, the O / U ratio is adjusted to 2.25 or less.
In the second step, 1200 to 18 in a reducing atmosphere.
By sintering at a high temperature of 00 ° C., the compact heated in the first step is densified in the state of the UO 2 phase as it is, and the O / U ratio of the pellet is adjusted to 2.00.
【００１１】[0011]
【実施例】以下、本発明を実施例により説明する。本発
明はこれらの実施例により制限されない。 ＜実施例１＞遊離のフッ酸を含まない１００ｇＵ／Ｌ濃
度のＵＯ2Ｆ2溶液と２８％のアンモニア水の反応により
生成した重ウラン酸アンモニウムを焙焼還元して比表面
積が約１０ｍ2／ｇのＵＯ2粉末を得た。この粉末に気孔
形成剤として平均粒径が１０〜１００μｍのシュウ酸ア
ンモニウムを１．０重量％の割合で添加した。この粉末
を大気中で数日間保管して、成形圧３ｔ／ｃｍ2で成形
した。図１に示すように、この成形体を室温（約２５
℃）の飽和水蒸気で加湿した水素気流中で６００℃／ｈ
の昇温速度で７００℃まで加熱し、そこで１時間保持し
た後、同じ昇温速度と雰囲気で１７５０℃まで加熱して
そこで４時間保持した。続いて６００℃／ｈの降温速度
により加湿した水素気流中で室温まで冷却してＵＯ2ペ
レットを得た。EXAMPLES The present invention will be described below with reference to examples. The invention is not limited by these examples. <Example 1> Ammonium diuranate produced by the reaction of a 100 gU / L UO 2 F 2 solution containing no free hydrofluoric acid with 28% ammonia water was roasted and reduced to have a specific surface area of about 10 m 2 / g of UO 2 powder was obtained. Ammonium oxalate having an average particle diameter of 10 to 100 μm was added to the powder as a pore forming agent at a ratio of 1.0% by weight. The powder was stored in the air for several days and molded at a molding pressure of 3 t / cm 2 . As shown in FIG.
600 ° C / h in a hydrogen stream humidified with saturated steam (° C)
The temperature was raised to 700 ° C. and held for 1 hour, and then the temperature was raised to 1750 ° C. and held there for 4 hours. Subsequently, UO 2 pellets were obtained by cooling to room temperature in a humidified hydrogen stream at a temperature decrease rate of 600 ° C./h.
【００１２】＜実施例２＞実施例１と同様にして得られ
たＵＯ2粉末を実施例１と同様に成形した。図２に示す
ように、この成形体を室温から６００℃／ｈの昇温速度
により二酸化炭素と一酸化炭素の混合比が１０対１の混
合気流中で７００℃まで加熱し、そこで１時間保持した
後、一酸化炭素のみの雰囲気に切換えて同じ昇温速度で
１７５０℃まで加熱してそこで４時間保持した。続いて
６００℃／ｈの降温速度により一酸化炭素のみの雰囲気
で室温まで冷却してＵＯ2ペレットを得た。Example 2 UO 2 powder obtained in the same manner as in Example 1 was molded in the same manner as in Example 1. As shown in FIG. 2, this molded body was heated from room temperature to 700 ° C. in a mixed air stream having a mixing ratio of carbon dioxide and carbon monoxide of 10: 1 at a heating rate of 600 ° C./h, and kept there for 1 hour. After that, the atmosphere was changed to only carbon monoxide, and the mixture was heated to 1750 ° C. at the same heating rate and kept there for 4 hours. Then, it was cooled to room temperature in a carbon monoxide only atmosphere at a temperature decrease rate of 600 ° C./h to obtain UO 2 pellets.
【００１３】＜比較例１＞実施例１と同様にして得られ
たＵＯ2粉末を実施例１と同様に成形した。図３に示す
ように、成形後、直ちにこの成形体を室温から６００℃
／ｈの昇温速度により飽和水蒸気で加湿した水素気流中
で１７５０℃まで加熱してそこで４時間保持した。続い
て６００℃／ｈの降温速度により加湿した水素気流中で
室温まで冷却してＵＯ2ペレットを得た。Comparative Example 1 UO 2 powder obtained in the same manner as in Example 1 was molded in the same manner as in Example 1. As shown in FIG. 3, immediately after molding, the molded body was heated from room temperature to 600 ° C.
It was heated to 1750 ° C. in a hydrogen stream moistened with saturated steam at a heating rate of / h and held there for 4 hours. Subsequently, UO 2 pellets were obtained by cooling to room temperature in a humidified hydrogen stream at a temperature decrease rate of 600 ° C./h.
【００１４】実施例１、実施例２及び比較例１の３種類
のＵＯ2ペレットについて、その原料のＵＯ2粉末のＯ／
Ｕ比、焼結体であるペレットの割れの有無、焼結密度、
結晶粒径及び焼結体のＯ／Ｕ比を測定した。その結果を
表１に示す。また、７００℃の中間保持直後のＯ／Ｕ比
を調べるため、実施例１及び実施例２の中間保持した成
形体をそれぞれ７００℃から室温まで急冷した。これら
のＯ／Ｕ比を表１の※印の箇所に示す。 （以下、余白）Regarding the three types of UO 2 pellets of Example 1, Example 2 and Comparative Example 1, the O / O of the raw material UO 2 powder was used.
U ratio, presence / absence of cracks in pellets that are sintered bodies, sintering density,
The crystal grain size and the O / U ratio of the sintered body were measured. The results are shown in Table 1. Further, in order to examine the O / U ratio immediately after the intermediate holding at 700 ° C., each of the molded bodies of Example 1 and Example 2 held intermediately was rapidly cooled from 700 ° C. to room temperature. These O / U ratios are shown in Table 1 at the points marked with *. (Hereafter, margin)
【００１５】[0015]
【表１】 [Table 1]
【００１６】表１の結果から、Ｏ／Ｕ比の高い粉末を成
形した成形体を中間保持することなく焼結する比較例１
では焼結後のペレットに割れが入るのに対して、焼結に
入る前に還元雰囲気で中間保持状態を入れてＯ／Ｕ比の
増加を防ぎ、その後焼結する処理を行った実施例１及び
実施例２では焼結密度及び結晶粒径に悪影響を与えるこ
となく、焼結体であるペレットの割れの発生を防止する
ことが可能であることが判った。From the results shown in Table 1, Comparative Example 1 in which a compact formed from a powder having a high O / U ratio was sintered without intermediate holding
In contrast to the case where cracks occur in the pellets after sintering, an intermediate holding state is put in a reducing atmosphere to prevent an increase in the O / U ratio before the sintering, and then the sintering is performed. Further, in Example 2, it was found that it is possible to prevent the occurrence of cracks in the pellet, which is a sintered body, without adversely affecting the sintered density and the crystal grain size.
【００１７】[0017]
【発明の効果】以上述べたように、本発明によれば、活
性度の大きなＵＯ2粉末の成形体を５００〜１０００℃
の温度範囲で加熱還元した後、１２００〜１８００℃の
温度範囲の還元雰囲気中で焼結することにより、結晶粒
径の大きなＵＯ2ペレットを割れや欠けのない状態で製
造することができる。また、気孔形成剤を添加した上記
ＵＯ2粉末の成形体を焼結することにより、所定の焼結
密度を有しかつ割れや欠けのない大粒径のＵＯ2ペレッ
トを製造して高燃焼度化の燃料として有効に利用するこ
とができる。As described above, according to the present invention, a UO 2 powder compact having a high activity is formed at 500 to 1000 ° C.
After heat-reducing in the temperature range of 1, and sintering in a reducing atmosphere in the temperature range of 1200 to 1800 ° C., UO 2 pellets having a large crystal grain size can be produced without cracks or chips. Further, by sintering the above-mentioned UO 2 powder compact to which a pore-forming agent is added, large-sized UO 2 pellets having a predetermined sintering density and free from cracks and chips are produced to obtain a high burnup. It can be effectively used as a fuel for chemicals.
【図１】本発明実施例１の成形体の熱処理状況を示すタ
イムチャート。FIG. 1 is a time chart showing a heat treatment state of a molded body of Example 1 of the present invention.
【図２】本発明実施例２の成形体の熱処理状況を示すタ
イムチャート。FIG. 2 is a time chart showing a heat treatment state of a molded body of Example 2 of the present invention.
【図３】本発明比較例１の成形体の熱処理状況を示すタ
イムチャート。FIG. 3 is a time chart showing the heat treatment state of the molded body of Comparative Example 1 of the present invention.
Claims (5)
の成形体を焼結して結晶粒径の大きなＵＯ2ペレットを
製造する核燃料ペレットの製造方法において、 前記成形体を５００〜１０００℃の温度範囲で加熱還元
することによりＯ／Ｕ比を２．２５以下に調節する第１
工程と、 前記還元した成形体を１２００〜１８００℃の温度範囲
の還元雰囲気中で焼結することによりＯ／Ｕ比が２．０
０の焼結ペレットを得る第２工程とを含むことを特徴と
する核燃料ペレットの製造方法。1. A method for producing nuclear fuel pellets, comprising molding UO 2 powder having a high activity and sintering the molded body to manufacture UO 2 pellets having a large crystal grain size. The O / U ratio is adjusted to 2.25 or less by heating and reducing in the temperature range of 1st.
And an O / U ratio of 2.0 by sintering the reduced compact in a reducing atmosphere in a temperature range of 1200 to 1800 ° C.
And a second step of obtaining sintered pellets of No. 0.
ｍｏｌ以下の酸素ポテンシャルである請求項１記載の核
燃料ペレットの製造方法。2. The reducing atmosphere in the first step is -210 kJ /
The method for producing a nuclear fuel pellet according to claim 1, wherein the oxygen potential is mol or less.
ｍｏｌ以下の酸素ポテンシャルである請求項１記載の核
燃料ペレットの製造方法。3. The reducing atmosphere in the second step is -340 kJ /
The method for producing a nuclear fuel pellet according to claim 1, wherein the oxygen potential is mol or less.
素とスチームの混合ガス雰囲気である請求項１記載の核
燃料ペレットの製造方法。4. The method for producing nuclear fuel pellets according to claim 1, wherein the reducing atmosphere in the first step or the second step is a mixed gas atmosphere of hydrogen and steam.
酸化炭素と二酸化炭素の混合ガス雰囲気である請求項１
記載の核燃料ペレットの製造方法。5. The reducing atmosphere in the first step or the second step is a mixed gas atmosphere of carbon monoxide and carbon dioxide.
A method for producing a nuclear fuel pellet as described.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5206768A JPH0761820A (en) | 1993-08-23 | 1993-08-23 | Production of nuclear fuel pellet |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5206768A JPH0761820A (en) | 1993-08-23 | 1993-08-23 | Production of nuclear fuel pellet |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0761820A true JPH0761820A (en) | 1995-03-07 |
Family
ID=16528772
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5206768A Withdrawn JPH0761820A (en) | 1993-08-23 | 1993-08-23 | Production of nuclear fuel pellet |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0761820A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006234753A (en) * | 2005-02-28 | 2006-09-07 | Global Nuclear Fuel-Japan Co Ltd | Manufacturing method of nuclear fuel pellet |
| JP2010190717A (en) * | 2009-02-18 | 2010-09-02 | Japan Atomic Energy Agency | Method for manufacturing nuclear fuel pellet for fast breeder reactors in fast breeder reactor cycle |
| JP2010190719A (en) * | 2009-02-18 | 2010-09-02 | Japan Atomic Energy Agency | Method for manufacturing nuclear fuel pellet for fast breeder reactors |
-
1993
- 1993-08-23 JP JP5206768A patent/JPH0761820A/en not_active Withdrawn
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006234753A (en) * | 2005-02-28 | 2006-09-07 | Global Nuclear Fuel-Japan Co Ltd | Manufacturing method of nuclear fuel pellet |
| JP4608337B2 (en) * | 2005-02-28 | 2011-01-12 | 株式会社グローバル・ニュークリア・フュエル・ジャパン | Method for producing nuclear fuel pellets |
| JP2010190717A (en) * | 2009-02-18 | 2010-09-02 | Japan Atomic Energy Agency | Method for manufacturing nuclear fuel pellet for fast breeder reactors in fast breeder reactor cycle |
| JP2010190719A (en) * | 2009-02-18 | 2010-09-02 | Japan Atomic Energy Agency | Method for manufacturing nuclear fuel pellet for fast breeder reactors |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A300 | Withdrawal of application because of no request for examination |
Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 20001031 |