JPS63205597A - Dry type enrichment adjusting method of uranium oxide - Google Patents
Dry type enrichment adjusting method of uranium oxideInfo
- Publication number
- JPS63205597A JPS63205597A JP62037882A JP3788287A JPS63205597A JP S63205597 A JPS63205597 A JP S63205597A JP 62037882 A JP62037882 A JP 62037882A JP 3788287 A JP3788287 A JP 3788287A JP S63205597 A JPS63205597 A JP S63205597A
- Authority
- JP
- Japan
- Prior art keywords
- uranium oxide
- concentration
- dry type
- adjusting method
- powder
- 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.)
- Pending
Links
- 238000000034 method Methods 0.000 title claims description 15
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 title claims description 6
- 229910000439 uranium oxide Inorganic materials 0.000 title claims description 6
- 239000000843 powder Substances 0.000 claims description 16
- 239000002245 particle Substances 0.000 description 5
- 229910002007 uranyl nitrate Inorganic materials 0.000 description 3
- 229910052770 Uranium Inorganic materials 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- SANRKQGLYCLAFE-UHFFFAOYSA-H uranium hexafluoride Chemical compound F[U](F)(F)(F)(F)F SANRKQGLYCLAFE-UHFFFAOYSA-H 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- 125000005289 uranyl group Chemical group 0.000 description 2
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000011812 mixed powder Substances 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 238000005453 pelletization Methods 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 238000003860 storage Methods 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
- Pharmaceuticals Containing Other Organic And Inorganic Compounds (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (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】
〔産業上の利用分野〕
本発明は濃縮度の異なる２種類以上の酸化ウラン粉末か
ら所望の濃縮度の酸化ウランを得る方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a method for obtaining uranium oxide with a desired enrichment from two or more types of uranium oxide powders with different enrichments.
原子炉には種々のｔＪ１度の酸化ウラン（ＵＯｚ）が用
いられる。これらυ０□は所定の濃縮度の六弗化ウラン
（ＬＩＦＩ、）を再転換することにより得られるが、こ
のＵＦ６は容器単位で購入されるため、必要量より条目
になるのが常であり、剰余のウランはＵＯ□として保管
されることになる。この剰余のＵＯｔは通常次の燃料交
換時に同一濃縮度のＵＯｚに混合して用いるので、保管
量は一定範囲内で増減するのみである。しかるに近年、
燃焼度の向上のために濃縮度の高いウランを用いる傾向
にあり、従来の種々の濃縮υ０．の中には使用見込みの
ないものが出て来た。このようなＵＯ２をそのまま保管
することは管理°上も経済的にも好ましくないことは言
うまでもない。そこでこれら使用見込みのないＵＯｚを
適宜混合して所望の濃縮度に調整することが検討されて
いる。Nuclear reactors use uranium oxide (UOz) of various tJ degrees. These υ0□ can be obtained by reconverting uranium hexafluoride (LIFI) at a predetermined enrichment level, but since this UF6 is purchased in containers, it is usually in pieces rather than the required amount. Surplus uranium will be stored as UO□. This surplus UOt is usually mixed with UOz of the same enrichment and used at the next fuel exchange, so the storage amount only increases or decreases within a certain range. However, in recent years,
There is a tendency to use highly enriched uranium to improve burnup, and conventional various enriched υ0. Some of them were found to have no hope of being used. It goes without saying that storing such UO2 as it is is undesirable both from a management and economic standpoint. Therefore, it is being considered to adjust the concentration to a desired level by appropriately mixing these UOz that are unlikely to be used.
このような濃縮度調整を最も確実に行えるのは、ＵＯｔ
を硝酸に熔解して硝酸ウラニル溶液とし、これらの溶液
を混合して所望の濃縮度の硝酸ウラニル溶液を得、該溶
液から００１を得る湿式法である。The most reliable method of concentration adjustment is UOt.
This is a wet method in which uranyl nitrate is dissolved in nitric acid to obtain a uranyl nitrate solution, these solutions are mixed to obtain a uranyl nitrate solution with a desired concentration, and 001 is obtained from the solution.
しかしながらこの方法によればｕＯ２粉末の濃縮度の均
一性は申し分ないが、工程が煩雑で、コスト高となるの
が避けられず、容易に採用し難い、一方複数種の濃縮度
の００．粉末をそのまま混合する乾式法も提案されてい
る（例えば特開昭５Ｌ１９７８９５号）。この方法はバ
ッチタイプ回転混合機によりＵＯ，粉末を混合後、破砕
機構を有するミキサーを通過せしめるものである。この
方法によれば筒便に濃縮度調整ができ、コスト的にも有
利であ、る。However, although the uniformity of the concentration of uO2 powder is satisfactory according to this method, the process is complicated and the cost is inevitably high, and it is difficult to easily adopt it. A dry method in which powders are mixed as they are has also been proposed (for example, Japanese Patent Application Laid-Open No. 5L197895). In this method, UO and powder are mixed in a batch type rotary mixer and then passed through a mixer having a crushing mechanism. According to this method, the concentration can be precisely adjusted and is advantageous in terms of cost.
しかしながらこの方法における破砕機構を有するミキサ
ーの採用は得られるＵＯ□粉末の粒子径を小さくし、ペ
レット強度に影響を与える恐れがある。However, the use of a mixer with a crushing mechanism in this method reduces the particle size of the obtained UO□ powder, which may affect pellet strength.
本発明の目的は、濃縮度の異なるＵＯｔ粉末を混合のみ
によって充分均一な濃縮度のＵＯ□粉末を得る方法を提
供することにある。An object of the present invention is to provide a method for obtaining UO□ powder with a sufficiently uniform concentration by simply mixing UOt powders with different concentrations.
上記目的を達成するため本発明の方法は、濃縮度の異な
る２種類以上のＵＯｔ粉末をスラブ型回転混合機により
混合する点に特徴がある。In order to achieve the above object, the method of the present invention is characterized in that two or more types of UOt powders having different concentrations are mixed using a slab-type rotary mixer.
スラブ型回転混合機は厚さを制限することにより臨界安
全が保たれるようになっている形状制限型の混合機であ
り、使用するＵ０８粉末の水分を管理しない場合の濃縮
度の最大値においても臨界上安全な厚さにしておけば装
入量に制限を加える必要がないという利点がある。この
ようなスラブ型回転混合機を用いて濃縮度の異なるＵＯ
□粉末の混合を行ったところ、比較的短時間で充分均一
混合し得ることが判明した。混合するＵＯｔ粉末の粒度
分布が互いに異っていても混合後のＵＯ□粉末の各粒度
における濃縮度は均一になる。この原因は明らかではな
いが、スラブ型回転混合機においては単なる機械的混合
のみでなく、ＵＯｔ粒子の会合、分散が効果的に行われ
るためと考えられる。The slab-type rotary mixer is a shape-limited mixer that maintains criticality safety by limiting the thickness, and at the maximum concentration when the moisture content of the U08 powder used is not controlled. There is an advantage that there is no need to limit the charging amount if the thickness is set to a criticalally safe thickness. Using such a slab-type rotary mixer, UO with different concentrations can be mixed.
□ When the powders were mixed, it was found that the mixture could be sufficiently uniformly mixed in a relatively short time. Even if the particle size distributions of the UOt powders to be mixed are different from each other, the degree of concentration at each particle size of the UO□ powder after mixing is uniform. Although the reason for this is not clear, it is thought that the slab-type rotary mixer not only performs mechanical mixing but also effectively associates and disperses UOt particles.
一辺２．５ｍの正方形の２主面を有し、厚さ１２（２）
で主面の対角線を水平回転軸とするスラブ型回転混合機
に、濃縮度が０．７１３％のＵＯ，粉末を８３３瞳、２
．６９１％ＵＯ２粉末を１６７ ｋｇ装入し、毎分４回
転で３０分間混合し、混合粉を２０メツシユの振動ふる
いを通して２５ｋｇずつ容器に受け、５０個の容器から
それぞれ５ｇずつ試料を採取して濃縮度を測定した。５
０点の試料の平均濃縮度は１．０３９％、標準偏差は０
．００３であった。又、別に各容器から５ｇずつ試料を
採取し、１００．２００及び３２５メツシユのふるいを
用いてふるい分けし、各粒度毎に濃縮度を測定した結果
を第１表に示す。It has two main faces of square shape with each side of 2.5 m, and the thickness is 12 (2).
The UO powder with a concentration of 0.713% was placed in a slab-type rotary mixer with the diagonal of the main surface as the horizontal axis of rotation.
．． Charge 167 kg of 691% UO2 powder, mix at 4 revolutions per minute for 30 minutes, pass the mixed powder through a 20-mesh vibrating sieve and receive 25 kg each into containers, then collect 5 g samples from each of the 50 containers and concentrate. The degree of 5
The average concentration of the sample with 0 points is 1.039%, and the standard deviation is 0.
．． It was 003. Separately, 5 g of sample was taken from each container and sieved using 100.200 and 325 mesh sieves, and the concentration was measured for each particle size. Table 1 shows the results.
第 １ 表
第１表からも濃縮度が殆んど均一になっていることが分
る。Table 1 It can be seen from Table 1 that the concentration is almost uniform.
本発明によれば混合のみによって濃縮度の調整が可能で
あり、破砕を伴わないのでｕＯ８粉末の物性が実用上全
く変らない。このため工程が著しく短縮され、ペレット
化の工程も全く通常品と同様に行うことができる。According to the present invention, the degree of concentration can be adjusted only by mixing, and since crushing is not involved, the physical properties of the uO8 powder do not change at all in practical terms. Therefore, the process is significantly shortened, and the pelletizing process can be performed in the same way as for ordinary products.
Claims (1)
回転混合機により混合することを特徴とする酸化ウラン
の乾式濃縮度調整方法。A dry enrichment adjustment method for uranium oxide, which comprises mixing two or more types of uranium oxide powders having different enrichments using a slab-type rotary mixer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62037882A JPS63205597A (en) | 1987-02-23 | 1987-02-23 | Dry type enrichment adjusting method of uranium oxide |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62037882A JPS63205597A (en) | 1987-02-23 | 1987-02-23 | Dry type enrichment adjusting method of uranium oxide |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63205597A true JPS63205597A (en) | 1988-08-25 |
Family
ID=12509908
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62037882A Pending JPS63205597A (en) | 1987-02-23 | 1987-02-23 | Dry type enrichment adjusting method of uranium oxide |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63205597A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2010006618A (en) * | 2008-06-24 | 2010-01-14 | Nuclear Fuel Ind Ltd | Method and apparatus for regulating uranium enrichment for high-temperature gas-cooled reactor |
-
1987
- 1987-02-23 JP JP62037882A patent/JPS63205597A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2010006618A (en) * | 2008-06-24 | 2010-01-14 | Nuclear Fuel Ind Ltd | Method and apparatus for regulating uranium enrichment for high-temperature gas-cooled reactor |
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