JPS6057040B2 - Method for producing molybdenum-99 using molybdenum trioxide pellets - Google Patents
Method for producing molybdenum-99 using molybdenum trioxide pelletsInfo
- Publication number
- JPS6057040B2 JPS6057040B2 JP9429878A JP9429878A JPS6057040B2 JP S6057040 B2 JPS6057040 B2 JP S6057040B2 JP 9429878 A JP9429878 A JP 9429878A JP 9429878 A JP9429878 A JP 9429878A JP S6057040 B2 JPS6057040 B2 JP S6057040B2
- Authority
- JP
- Japan
- Prior art keywords
- molybdenum
- pellets
- molybdenum trioxide
- producing
- 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.)
- Expired
Links
Landscapes
- Inorganic Compounds Of Heavy Metals (AREA)
Description
【発明の詳細な説明】
この発明はモリブデンー９９（以下’’９９Ｍｏ’’
と略記する場合がある）の製法に関する。DETAILED DESCRIPTION OF THE INVENTION This invention relates to molybdenum-99 (hereinafter referred to as ``99Mo'').
(sometimes abbreviated as ).
より詳細には、この発明はΞ酸化モリブデン（以下’’
ＭｏＯ。More specifically, the invention relates to Ξ molybdenum oxide (hereinafter referred to as ''
MoO.
’’と略記する場合がある）ペレツタを使つた”Ｍｏの
製法に関する。 従来、゜゜Ｍｏは、（イ）ウランー２
３５を使用し原子炉内で核分裂を起こさしめ、核分裂生
成物の一つとして生成する゜゜Ｍｏの化学分離する方法
や、（口）金属モリブデン（金属又は金属粉末）を原子
炉内で照射し、酸化後アルカリに溶かすか、硝酸溶解後
アルカリ性とする方法やレ→三酸化モリブデン粉末を容
器（アルミニウム製カプセル）に直接充填して原子炉照
射して、アルカリて溶解する方法によつて製造されてい
た。(sometimes abbreviated as ``'') using pellets. Conventionally, ゜゜Mo is (a) uranium-2.
35 to cause nuclear fission in a nuclear reactor and chemically separate ゜゜Mo, which is produced as one of the fission products. It is manufactured by dissolving it in alkali after oxidation, or by dissolving it in nitric acid and making it alkaline, or by filling molybdenum trioxide powder directly into a container (aluminum capsule), irradiating it in a nuclear reactor, and dissolving it in alkali. Ta.
然しながら、上述した従来技術には各々改良されるべ
き欠点があつた。However, each of the above-mentioned conventional techniques has drawbacks that should be improved.
即ち、ウランー２３５を使用する方法は照射中の発熱
および多量の放射能の中から゜゜Ｍｏだけを分離するた
めの複雑な化学処理が必要である。That is, the method using uranium-235 requires complicated chemical treatment to separate only °Mo from heat generated during irradiation and a large amount of radioactivity.
又、金属モリブデンを使用する方法は、照射容積は小さ
くてすむが、照射中の中性子自己しやへい効果が三酸化
モリブデンより大きく、９゜Ｍｏの比放射能（放射能を
もたないモリブデン中の放射能をもつ゜゜Ｍｏの割合）
が低い。また照射後の化学処理が、三酸化モリブデンヘ
の酸化や硝酸による溶解など複雑である。更に、Ξ酸化
モリブデン粉末を、そのまま使用する方法は、照射後容
器から試料をとり出す際、粉末のため放射能汚染が大き
いという欠点がある。 本発明の主要目的は上述した従
来技術の欠点を改良した新規なモリブデンー９９の製法
を提供する事である。In addition, the method using molybdenum metal requires a small irradiation volume, but the neutron self-suppression effect during irradiation is greater than that of molybdenum trioxide, and the specific activity of 9°Mo (in molybdenum, which has no radioactivity) is greater than that of molybdenum trioxide. Proportion of ゜゜Mo with radioactivity)
is low. In addition, the chemical treatment after irradiation is complicated, including oxidation of molybdenum trioxide and dissolution with nitric acid. Furthermore, the method of using Ξ molybdenum oxide powder as it is has the disadvantage that when the sample is taken out of the container after irradiation, radioactive contamination is large due to the powder. The main object of the present invention is to provide a new method for producing molybdenum-99 which overcomes the drawbacks of the prior art described above.
更に本発明の目的は三酸化モリブデン粉末をペレット
成型・焼結し、ターゲットとし、照射中の中性子自己し
やへい効果を小さくし、照射後の放射能汚染を小さくし
、化学処理を容易にしたＩＭｏの製造法を提供すること
である。 本発明で使用される三酸化モリブデンペレッ
トは、標示純度の高い三酸化モリブデン粉末に粘結材と
して２ｗ／ ｏの樟脳を溶解したエタノールを１５ｗ／
ｏ加え、３〜４日間放置した後、一定量を分取し金型
に入れ９８０に９１ｃｌｔの面圧を加えてペレットに成
形される。Furthermore, the purpose of the present invention is to pelletize and sinter molybdenum trioxide powder and use it as a target to reduce the neutron self-shielding effect during irradiation, reduce radioactive contamination after irradiation, and facilitate chemical processing. An object of the present invention is to provide a method for producing IMo. The molybdenum trioxide pellets used in the present invention are made by mixing 15 w/o of ethanol with 2 w/o of camphor dissolved in molybdenum trioxide powder with high labeled purity as a binding agent.
o, and after leaving it for 3 to 4 days, a certain amount is taken out and put into a mold, and a surface pressure of 91 clt is applied to 980 to form pellets.
この様にして製造されたペレットを６００〜７５０℃で
９紛間加熱・焼結し、水分、エタノール、樟脳を除去し
、硬度を高める。 上述した様にして得られた三酸化モ
リブデンをアルミニウム製容器に入れ、原子炉内で４〜
７日間照射し、アルミニウム製容器を開封後、アルカリ
（アンモニウム水又はカセイソーダ）で溶解し、″Ｍｏ
製品を得る。The pellets produced in this manner are heated and sintered at 600 to 750°C to remove moisture, ethanol, and camphor, and increase hardness. The molybdenum trioxide obtained as described above was placed in an aluminum container and heated in a nuclear reactor for 4 to 4 hours.
After irradiating for 7 days and opening the aluminum container, dissolve it in alkali (ammonium water or caustic soda) and
Get the product.
以下、実施例により本発明をより詳細に説明する。 Hereinafter, the present invention will be explained in more detail with reference to Examples.
実施例 １
市販の特級三酸化モリブデン粉末に、２Ｗ／０樺脳を溶
解したエタノール１５Ｗ／ｏ加え攪拌混合する。Example 1 15 W/o of ethanol in which 2 W/0 birch was dissolved was added to commercially available special grade molybdenum trioxide powder and mixed with stirring.
３日間自然乾燥した後、流動パラフィンで表面処理した
金型（１７．６５？φ）で約１６ｆを入れ、油圧機でペ
レット成型面圧９８０ｋ９１ｃｒ１の圧力を加え、グリ
ーンペレット（焼結前の成型しただけのペレット）を得
た。After air drying for 3 days, about 16 f was put into a mold (17.65?φ) whose surface was treated with liquid paraffin, and a pressure of 980k91cr1 was applied to form the pellet using a hydraulic machine. only pellets) were obtained.
このグリーンペレットを電気炉で７００℃、９紛間加熱
し、１個１６ｙの三酸化モリブデンペレット（外径１８
．１顛、高さ２２．５ｃｍ）を製作した。焼結後の三酸
化モリブデンペレットは密度が理論密度の５９％で２．
７′１ｃＴ１１硬度は２．５ｋ９定圧荷重硬度計で実測
した値が２０〜２５であり、金属鉛（２５．８）や金属
カドミウム（２７．３）より硬く、金属スズ（１２．１
）、金属銅（＆１）、金属アルミニウム（７．２）より
軟かであつた。These green pellets were heated in an electric furnace at 700°C, and one 16y molybdenum trioxide pellet (outer diameter 18
．． 1 size, height 22.5cm). After sintering, the molybdenum trioxide pellets have a density of 59% of the theoretical density.
7'1cT11 hardness has a value of 20 to 25 measured using a 2.5K9 constant pressure load hardness tester, which is harder than metal lead (25.8) and metal cadmium (27.3), and harder than metal tin (12.1).
), metallic copper (&1), and metallic aluminum (7.2).
焼結前後での寸法、重量変化は次表の通りであつた。The dimensions and weight changes before and after sintering are shown in the table below.
焼結後のペレットはドリルで穴をあけ、中空円筒ペレッ
トとする事も可能であつた。After sintering, the pellets could be made into hollow cylindrical pellets by drilling holes.
焼結後のペレットを原子炉で中性子照射した所、アンモ
ニア水に対する溶解上の変化もなく、通常の粉末三酸化
モリブデンの溶解と同一の条件で溶解出来た。When the sintered pellets were irradiated with neutrons in a nuclear reactor, there was no change in solubility in aqueous ammonia, and the pellets could be melted under the same conditions as for ordinary powdered molybdenum trioxide.
また、中性子の三酸化モリブデンによる自己しやへいか
らの９９Ｍ０の比放射能の低下割合も粉末を充填して照
射した場合とほぼ同じで、金属モリブデンの場合より約
３割優れている。またハンドリングによる放射能汚染も
粉末の場合により低下出来た。本発明による円柱又は中
空円筒ペレットの三酸化モリブデンターゲットを採用し
た９９Ｍ０製造法は金属モリブデンを採用する場合より
、比放射能の高い製品を安易な化学処理で実施できる点
で優れている。Furthermore, the rate of decrease in the specific radioactivity of 99M0 due to self-suppression of neutrons by molybdenum trioxide is almost the same as when irradiation is performed with powder filled, and is about 30% better than in the case of metal molybdenum. In addition, radioactive contamination due to handling was reduced in the case of powder. The 99M0 production method employing a cylindrical or hollow cylindrical pellet molybdenum trioxide target according to the present invention is superior to the method using metallic molybdenum in that it can produce products with high specific radioactivity through easy chemical treatment.
Claims (1)
子炉内照射することを特徴とするモリブデン−９９を製
造する方法。1. A method for producing molybdenum-99, which comprises irradiating molybdenum trioxide pellets in a nuclear reactor as a target.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9429878A JPS6057040B2 (en) | 1978-08-02 | 1978-08-02 | Method for producing molybdenum-99 using molybdenum trioxide pellets |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP9429878A JPS6057040B2 (en) | 1978-08-02 | 1978-08-02 | Method for producing molybdenum-99 using molybdenum trioxide pellets |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5522102A JPS5522102A (en) | 1980-02-16 |
| JPS6057040B2 true JPS6057040B2 (en) | 1985-12-12 |
Family
ID=14106355
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9429878A Expired JPS6057040B2 (en) | 1978-08-02 | 1978-08-02 | Method for producing molybdenum-99 using molybdenum trioxide pellets |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6057040B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62150851U (en) * | 1986-03-17 | 1987-09-24 | ||
| JP2010175409A (en) * | 2009-01-30 | 2010-08-12 | Japan Atomic Energy Agency | METHOD FOR PRODUCING HIGH-DENSITY AND HIGH-PURITY (n, gamma)99Mo AND HIGH-DENSITY AND HIGH-PURITY (n, gamma)99Mo PRODUCED BY THE METHOD |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4618732B2 (en) * | 2006-10-20 | 2011-01-26 | 独立行政法人 日本原子力研究開発機構 | Method and apparatus for manufacturing radioactive molybdenum |
| WO2012039036A1 (en) * | 2010-09-22 | 2012-03-29 | 独立行政法人放射線医学総合研究所 | Process and device for production of radionuclide using accelerator |
| JP6465284B2 (en) * | 2014-12-08 | 2019-02-06 | 国立研究開発法人日本原子力研究開発機構 | Method for producing molybdenum trioxide pellets |
| JP7187750B2 (en) * | 2018-09-27 | 2022-12-13 | 久幸 末松 | Production method and target material for radioactive isotope Mo-99 |
-
1978
- 1978-08-02 JP JP9429878A patent/JPS6057040B2/en not_active Expired
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62150851U (en) * | 1986-03-17 | 1987-09-24 | ||
| JP2010175409A (en) * | 2009-01-30 | 2010-08-12 | Japan Atomic Energy Agency | METHOD FOR PRODUCING HIGH-DENSITY AND HIGH-PURITY (n, gamma)99Mo AND HIGH-DENSITY AND HIGH-PURITY (n, gamma)99Mo PRODUCED BY THE METHOD |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5522102A (en) | 1980-02-16 |
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