201141791 六、發明說明： 【發明所屬之技術領域】 本發明係關於一種獲取高純度銅-64同位素之方法，尤 其是關於一種從鋅-68獲取鎵_67同位素的過程所產生之酸 流洗廢液中獲取高純度銅-64同位素的方法。 【先前技術】 近年來，正子斷層攝影（Positron Emission Tomography，簡稱PET)以飛快的速度崛起，成為醫學上一 項重要的診斷造影模式，主要被用來確定癌症的發生與嚴 重性、神經系統的狀況以及心血管方面的疾病。目前PET 已被公認在某些疾病判定方面特別有效，包括判斷癌症是 否存在，是否已擴散轉移，對治療是否有所反應，檢查癌 症是否復發以及病患在治療後是否已不再有癌細胞，使用 PET特別有效的癌症包括肺癌、頭頸癌、大腸直腸癌、食 道癌、淋巴瘤、黑色素瘤、乳癌、曱狀腺癌、子宮頸癌、 胰臟癌以及腦瘤。 簡言之，使用PET造影，需在病人身上注射放射性藥 物，放射性藥物在病人體内釋出訊號，而被體外的PET掃 瞄儀所接收，繼而形成影像，利用PET所攝得的影像可顯 現出器官或組織（如腫瘤）的化學變化。 再者，放射性同位素依其釋出之輻射線種類之不同， 研製成核醫藥物劑型後，可應用於疾病之診斷或治療。迴 旋加速器為臨床核醫藥物之重要同位素產生器，可產製鉈 201141791 •20卜銦·111、蛾.123、ftM8及鎵·67等中長半衰期同位素， ^及碳·1卜氧·15及氮-13等短半衰期之核種，應用於心血 管疾病、曱狀腺功能、腫瘤、發炎及代謝疾病等等之診斷。 隨著核子醫學之進展與臨床之需求，迴旋加速器除了 診斷用同位素之研製，對於治療用同位素之產製與應用亦 漸受注意，其中兼具診斷與治療功能之放射性同位素銅_64 尤其受到重視。銅-64的半衰期適中（12.7小時），可以釋出 511keV的能量，適合於ρΕτ造影，亦可釋放1346]^¥之 貝它射線，兼具治療之潛力e64Cu結合上適當之配位子（例 如小分子化合物、胜肽或單株抗體）可應用於疾病之診斷或 治療用途’例如，應用於心臟灌注造影的64CU-PTSM，缺 氧造衫劑的 Cu-ATSM ’用於偵測多重抗藥性(multidrug resistance)的 64Cu-bis(diphosphine) complexes，用於内分泌 腫瘤之診療用64Cu-TETA-Octreotide，缺氧標把治療的 64Cu-diacetyl-bis(N-methylthiosemicarba-zone)，64Cu 標幟單 株抗體則可應用於放射免疫製劑。 由於64Cu之半衰期僅為12.7小時，不易保存，有鑑 於此，通常以30 MeV中型迴旋加速器進行銅_64同位素之 研製，其係將高豐度穩定同位素鎳-64電鍍於固體靶後，以 15〜18MeV的質子射束照射’再經分離純化步驟，可獲得 高純度之放射性同位素銅-64。但是，高豐度穩定同位素的 鎳-64價格相當昂貴，為節省成本’仍積極思考其它產製銅 -64放射性同位素的方法。 另一方面，鎵-67(67Ga)為重要的醫用放射性同位素之 一，目前既有技術已建立以鋅-68固體靶經迴旋加速器照射 201141791 研製鎵-67同位素的技術’研製成67_咖核醫藥物的 生產’廣泛應用於感染、發炎及淋巴癌等診斷。參考辞.Μ 的核反應圖，可知其產生之核種除了鎵_66、鎵以及録 68外’另-重要的產物即為鋼_64，以往為取得高純度之 鎵-67同位素，銅-64被視為核種不純物而將之分離至声取 鎵-67製程中的酸流洗廢液（以下簡麟_67酸流洗廢液)又内。 有鑑於此，乃思考自鎵·67酸流洗廢液回收並純化出 銅-64的技術。該技術將可建立鋅_68靶材同時產製兩種且 有應用價值的放射性同位素鎵_67以及蛛64，能為核醫藥 物研發及疾病的診療帶來新的契機。 【發明内容】 本發明提供一種獲取高純度鋼_64同位素之方法，其係 利用質子束照射鋅-68固體靶，除了利用已建立的技術例行 生產同位素鎵-67外，本發明乃自鋅_68研製鎵_67所產生 之鎵-67酸流洗廢液中’進-步利用離子交換樹脂分離純化 技術，獲得另一種同位素銅-64 ’其核種純度高於99%。 【實施方式】 為使貴審查委員能對本發明之特徵、目的及功能有 更進-步的認知與瞭解，下文特將本發明之方法的相關細 部結構以及設計的理念原由進行說明，以使得審查委員可 以了解本發明之特點，詳細說明陳述如下： — 本發明提供一種獲取高純度銅-64同位素之方法，尤其 是指一種從鋅-68獲取鎵-67同位素的過程所產生之酸流^ 201141791 廢液中獲取高純度銅_64同位素的方法。 圖一係為習知技術利用鋅-68獲取鎵-67同位素之方法 的流程示意圖。如圖一所示，利用辞-68獲取鎵_67同位素 之方法1包括下列步驟： 步驟11 :提供一鍍有辞-68之銅基銀靶； 步驟12 :以質子束照射該鍍有鋅-68之銅基銀乾； 步驟13 :對該鍍有鋅-68之銅基銀靶進行獲取鎵_67 同位素之酸洗以及純化程序；以及 步驟14 :收集鎵-67酸流洗廢液。 如圖一所示之步驟11〜14，本發明係採迴旋加速器之 銅基銀乾’在步驟11先將尚豐度的辞-68(豐度大於98%以 上）電鑛於該銅基銀乾之把面上，送入該迴旋加速器之照射 靶站，接著在步驟12經29±2MeV的質子撞擊反應，接著 在步驟13以當量濃度9N的HCL溶液溶解後，經由化學純 化分離程序，得到鎵-67同位素，然後在步驟14收集錁-67 酸流洗廢液。 接著，將前述之9NHC1流洗廢液（即步驟14所收集之 鎵-67酸流洗廢液）先通過陽離子交換樹脂（AG50W-X2, 100-200mesh，hydrogen form)，再通過陰離子交換樹脂(AG 1-X8，100-200 mesh，chloride form，Bio-Rad)，以進行高核 種純度之銅-64同也素的回收純化，並去除鎵_67/68等核種 不純物。圖二係為本發明獲取高純度銅_64同位素之方法的 流程示意圖。如圖二所示，本發明獲取高純度鋼_64同位素 之方法2包括下列步驟： 201141791 步驟21 :提供一鎵-67酸流洗廢液； 步驟22 :以一條件化溶液將一第一離子交換樹脂與 一第二離子交換樹脂活化； 步驟23 :將該錄-67酸流洗廢液通過一充填有該第一 離子交換樹脂之第一管柱，並繼續加入適量之特 定濃度的HC1溶液清洗該第一管柱，並收集該第 一管柱之流出液； 步驟24.將第一管柱之流出液通過一充填有第二離 子交換樹脂之第二管柱’並繼續加入適量之特定濃 度的HC1溶液清洗該第二管柱，並收集該第二管柱 之流出液；以及 步驟25 :取適量之特定濃度之HC1溶液加入該第二 管柱，並收集矣流虫液。 以下以實際之實施例詳細說明之。 在步驟21將上述步驟14所收集之鎵_67酸流洗廢液取 20毫升（以下將「毫升」簡稱ml)，準備進行後續步驟，以 從中獲取rfj純度銅·64同位素。 在上述步驟22本發明之實施方式中，第一離子交換樹 脂係為一陽離子交換樹脂（AG50W-X2，100-200mesh, hydrogen form)，第二離子交換樹脂係為一陰離子交換樹脂 (AG 1-X8, 100-200 mesh, chloride form，Bio-Rad)。但是， 實際之操作順序並不以此為限，第一離子交換樹脂亦可為 一陰離子交換樹脂’此時第二離子交換樹脂則為一陽離子 交換樹脂。 S.1201141791 VI. Description of the Invention: [Technical Field of the Invention] The present invention relates to a method for obtaining a high-purity copper-64 isotope, and more particularly to an acid stream washing waste process for obtaining a gallium-67 isotope from zinc-68. A method for obtaining a high-purity copper-64 isotope in a liquid. [Prior Art] In recent years, Positron Emission Tomography (PET) has emerged at a rapid rate and has become an important diagnostic angiography model in medicine. It is mainly used to determine the occurrence and severity of cancer and the nervous system. Conditions and cardiovascular diseases. At present, PET has been recognized as particularly effective in determining certain diseases, including judging whether cancer is present, whether it has spread and metastasized, responding to treatment, checking whether cancer has recurred, and whether the patient no longer has cancer cells after treatment. Cancers that are particularly effective with PET include lung cancer, head and neck cancer, colorectal cancer, esophageal cancer, lymphoma, melanoma, breast cancer, squamous cell carcinoma, cervical cancer, pancreatic cancer, and brain tumors. In short, the use of PET imaging requires the injection of radiopharmaceuticals into the patient. The radioactive drug releases the signal in the patient's body and is received by the external PET scanner, which in turn forms an image. The image taken with PET can be visualized. Chemical changes in organs or tissues such as tumors. Furthermore, radioisotopes can be applied to the diagnosis or treatment of diseases after the development of nucleating pharmaceutical dosage forms depending on the type of radiation they emit. The cyclotron is an important isotope generator for clinical nuclear medicine. It can produce mid-length half-life isotopes such as 201141791 • 20 indium·111, moth.123, ftM8 and gallium·67, and carbon·1 octa·15. A short-lived nuclear species such as nitrogen-13, which is used for the diagnosis of cardiovascular diseases, verrucous function, tumors, inflammation and metabolic diseases. With the advancement of nuclear medicine and clinical needs, in addition to the development of diagnostic isotopes, cyclotrons have received increasing attention for the production and application of therapeutic isotopes. Among them, radioisotope copper, which has both diagnostic and therapeutic functions, is particularly valued. . Copper-64 has a moderate half-life (12.7 hours), can release 511 keV of energy, is suitable for ρΕτ angiography, and can release 1346]^¥ of the beta ray, which has the potential to treat e64Cu combined with appropriate ligands (eg Small molecule compounds, peptides or monoclonal antibodies) can be used for the diagnosis or therapeutic use of diseases 'for example, 64CU-PTSM for cardiac perfusion imaging, Cu-ATSM for hypoxic lacquers' for detecting multiple drug resistance 64Cu-bis (diphosphine) complexes (multidrug resistance) for the diagnosis and treatment of endocrine tumors 64Cu-TETA-Octreotide, 64Cu-diacetyl-bis (N-methylthiosemicarba-zone), 64Cu-labeled single plant Antibodies can be applied to radioimmunoassays. Since the half-life of 64Cu is only 12.7 hours, it is difficult to store. In view of this, the development of copper _64 isotope is usually carried out with a 30 MeV medium cyclotron, which is electroplated with a high-abundance stable isotope nickel-64 on a solid target. ~18MeV proton beam irradiation' is then separated and purified to obtain high purity radioisotope copper-64. However, nickel-64, a high-abundance stable isotope, is quite expensive and is cost-effective. Still thinking about other methods of producing copper-64 radioisotopes. On the other hand, gallium-67 (67Ga) is one of the important medical radioisotopes. At present, the technology has been established to develop the gallium-67 isotope by the zinc-68 solid target by cyclotron irradiation 201141791. The production of nuclear medicine is widely used in the diagnosis of infection, inflammation and lymphoma. With reference to the nuclear reaction diagram of 辞.Μ, it can be seen that the nucleus produced by the nucleus except for gallium _66, gallium and recorded 68 is another important product, namely steel _64. In the past, the high-purity gallium-67 isotope was obtained. It is considered as a nuclear impurity and is separated into the acid flow washing waste liquid (hereinafter, the simple _67 acid flow washing waste liquid) in the so-called gallium-67 process. In view of this, it is considered to recover and purify copper-64 from gallium 67 acid washing waste liquid. This technology will establish a zinc-68 target and produce two kinds of useful radioisotope gallium _67 and spider 64, which will bring new opportunities for the development of nuclear medicine and the diagnosis and treatment of diseases. SUMMARY OF THE INVENTION The present invention provides a method for obtaining a high-purity steel _64 isotope by irradiating a zinc-68 solid target with a proton beam, except that the isotope gallium-67 is routinely produced by an established technique, and the present invention is derived from zinc. _68 Developed gallium-67 acid flow washing waste liquid produced by gallium _67 'in step-by-step separation and purification technology using ion exchange resin to obtain another isotope copper-64' whose nuclear purity is higher than 99%. [Embodiment] In order to enable the reviewing committee to have a further understanding and understanding of the features, objects and functions of the present invention, the detailed structure of the method of the present invention and the concept of the design are explained below for the purpose of review. Members can understand the characteristics of the present invention, and the detailed description is as follows: - The present invention provides a method for obtaining a high-purity copper-64 isotope, in particular, an acid stream generated by a process for obtaining a gallium-67 isotope from zinc-68 ^ 201141791 A method for obtaining high-purity copper _64 isotope in waste liquid. Figure 1 is a schematic flow diagram of a conventional method for obtaining a gallium-67 isotope using zinc-68. As shown in FIG. 1, the method 1 for obtaining a gallium_67 isotope using the word -68 includes the following steps: Step 11: providing a copper-based silver target plated with -68; Step 12: irradiating the plated zinc with a proton beam 68 copper-based silver stem; Step 13: The zinc-based copper-plated silver target is subjected to a pickling and purification procedure for obtaining a gallium-67 isotope; and step 14: collecting a gallium-67 acid stream washing waste liquid. As shown in FIG. 1 , steps 11 to 14 , the present invention is a copper-based silver stem of a cyclotron. In step 11, the energy of the abundance of -68 (abundance greater than 98%) is firstly electrolyzed to the copper-based silver. The dry surface is sent to the irradiation target station of the cyclotron, and then subjected to a proton collision reaction of 29±2 MeV in step 12, followed by dissolution in an equivalent concentration of 9N HCL solution in step 13, and then subjected to a chemical purification separation procedure. The gallium-67 isotope is then collected in step 14 for the 锞-67 acid stream washing waste. Next, the aforementioned 9NHC1 flow washing waste liquid (ie, the gallium-67 acid flow washing waste liquid collected in step 14) is first passed through a cation exchange resin (AG50W-X2, 100-200 mesh, hydrogen form), and then passed through an anion exchange resin ( AG 1-X8, 100-200 mesh, chloride form, Bio-Rad), for the recovery and purification of copper-64 isoforms of high nuclear purity, and removal of nuclear impurities such as gallium_67/68. Figure 2 is a schematic flow diagram of a method for obtaining a high purity copper _64 isotope according to the present invention. As shown in FIG. 2, the method 2 for obtaining a high-purity steel _64 isotope comprises the following steps: 201141791 Step 21: providing a gallium-67 acid flow washing waste liquid; Step 22: using a conditioning solution to form a first ion The exchange resin is activated with a second ion exchange resin; Step 23: passing the recorded -67 acid rinse waste liquid through a first column packed with the first ion exchange resin, and continuing to add an appropriate amount of the specific concentration of the HC1 solution Washing the first column and collecting the effluent of the first column; Step 24. Passing the effluent of the first column through a second column filled with a second ion exchange resin' and continuing to add an appropriate amount of specific The second column is washed with a concentration of HC1 solution, and the effluent of the second column is collected; and step 25: an appropriate amount of a certain concentration of the HC1 solution is added to the second column, and the turbulent liquid is collected. The following is a detailed description of the actual embodiment. In step 21, 20 ml of the gallium_67 acid washing waste liquid collected in the above step 14 is taken (hereinafter referred to as "ml" as abbreviated as ml), and a subsequent step is prepared to obtain the rfj purity copper·64 isotope therefrom. In the above step 22, in the embodiment of the invention, the first ion exchange resin is a cation exchange resin (AG50W-X2, 100-200 mesh, hydrogen form), and the second ion exchange resin is an anion exchange resin (AG 1- X8, 100-200 mesh, chloride form, Bio-Rad). However, the actual operation sequence is not limited thereto, and the first ion exchange resin may be an anion exchange resin. The second ion exchange resin is a cation exchange resin. S.1
本實施例在步驟22之條件化溶液係使用當量濃度9N ·[ 7 201141791 的HC1溶液，分別取30ml通過該陽離子交換樹脂與該陰 離子交換樹脂，使該陽離子交換樹脂與該陰離子交換樹脂 活化，以進行從鎵-67酸流洗廢液純化分離銅-64同位素的 程序。 然後進行步驟23，將步驟21所提供之20ml鎵-67酸 流洗廢液，通過一充填有陽離子交換樹脂之第一管柱，並 繼續加入10ml之當量濃度9N的HC1溶液清洗該第一管 柱，並收集該第一管柱之流出液。 然後進行步驟24，將該第一管柱之流出液通過一充填 有陰離子交換樹脂之第二管柱，並繼續加入40ml之當量濃 度9N的HC1溶液清洗該第二管柱，並收集該第二管柱之流 出液。 接著進行步驟25，取適量之當量濃度1N或2N之HC1 溶液加入該第二管柱，並收集該第二管柱之流出液。該流 出液即含有高純度銅-64同位素。 在步驟25取得含有高純度銅-64同位素之流出液後， 使用者可以根據其濃度需求，再進行濃縮除酸的步驟以得 到不同濃度之高純度銅-64同位素，濃縮除酸的方法在習 知技術已多有揭露，在此不再贅述。 穩定同位素鋅-68經迴旋加速器照射後，未反應之鋅 -68必須回收再利用。因此在步驟25取得含有高純度銅-64 同位素之流出液後，可以對該第二管柱繼續加入適量的（在 本實施例使用120ml)水，並收集其流出液，即可得鋅-68 收集液，再經適當濃縮處理後，即可回收再度用於固體的 銅基銀靶之電鍍。其中，濃縮處理的方法在習知技術已多 201141791 有揭露，在此不再贅述。 本發明亦進行實驗測試’將鎵-67酸流洗廢液通過陽離 • 子父換樹脂（AG 50W-X2，100〜2〇〇 mesh，hydrogen form)， 以分析對於銅-64之回收率的影響，所有樣品皆以多頻道脈 高能譜分析儀（Multi-Channel Analyzer，以下簡稱MCA )進 行核種分析鑑定，結果顯示陽離子交換樹脂可使銅·64回收 率達98%以上，而鎵-67之去除率則達95%以上。將前述所 得之收集液’再經陰離子交換樹脂(AG 1-Χ8, 100-200 mesh， • chloride form)做進一步分離純化，實驗結果顯示鎵-67可以 進一步去除’銅-64回收率為97%以上，顯示經由陽、陰離 子兩階段交換樹脂的分離純化銅-64，可提高銅-64的回收 率’且銅-64核種純度高達99.5%以上。 此外，為求最佳分離條件，本發明同時進行陰陽離子 交換樹脂之不同充填管柱規格對於銅·64分離之影響。首先 比較陽離子交換樹脂之兩種内徑〇.5cin以及lcm之管柱（長 度皆為15cm)的差異’實驗顯示兩者之銅_64流洗率皆大於 • 99%，兩種管柱内徑皆適合使用。然後再比較陰離子交換 樹脂，在此使用三種規格之管柱，分別為：（丨）内徑〇 5cmX 長度10cm、（2)内徑lcmx長度l〇cm以及（3)内徑lcmx長度 15cm，分析結果顯示銅-64吸附率分別為（1) 98.5%、（2) 99.5%以及（3) 99.99%，皆合適當做陰離子交換樹脂之管柱 規格。 再者’比較不同酸度之HC1淘洗液對銅-64收集率之 影響。圖三係顯示本發明使用不同酸度HC1淘洗液對銅-64 收集率之效果關係圖。如圖三所示，當量濃度1N及2N的 201141791 HC1淘洗液的銅-64收集率相似，大多集中於前20mL，相 反地，使用當量濃度3N的Ηα淘洗液時，銅-64較慢出現 且分佈較廣，造成流洗液體積較多，不利於後續濃縮除酸 之執行。 穩定同位素鋅-68經迴旋加速器照射後，未反應之鋅 -68必須回收再利用，以節省鋅-68之使用量。本發明同時 分析不同酸度之HC1淘洗液對於鋅-68回收率之影響。因 一物質的回收率可從其在溶液中的活度反映出，所以，圖 四係顯示本發明使用不同酸度HC1淘洗液對鋅-68回收率 之效果關係圖。如圖四所示’以當量濃度2Ν的HC1淘洗 液之鋅-68回收率略高於1Ν的HC1淘洗液之結果，但不具 統計之差異性，顯示以當量濃度1Ν及2Ν的HC1淘洗液 皆為合適之流洗液。 如以上實驗的結果所示，使用當量濃度1Ν或2Ν的 HC1淘洗液之流洗結果較3Ν的HC1淘洗液更理想，銅大 量被洗出，鋅及鎵則都被吸附於管柱内’繼續以水為洗流 液時，則鋅大量被洗出。因此，本發明可以先使用當量濃 度1Ν或2Ν的HC1淘洗液作為洗流層析管挺的溶液，以 吸附住鎵-67及鋅-68，而且洗流出銅-64，達到純化核種之 目的，接著將該陰離子交換樹脂繼續使用水進行流洗，藉 以回收鋅-68。 本發明亦可用於建立鉛室内之半自動化同位素麵 的生產技術’產量穩定且品質優異。本發明不僅可節省 定同位素鋅-68之使用量，且可提升加速器使用之效率穩 其能一次照射獲得兩種醫用同位素鎵·67與麵]-64， ’使 建到節 10 201141791 能之目的，自動化設計並能降低工作人員之輻射劑量，深 具應用潛力。 惟以上所述者，僅為本發明之實施例，當不能以之限 制本發明範圍。即大凡依本發明申請專利範圍所做之均等 變化及修飾，仍將不失本發明之要義所在，亦不脫離本發 明之精神和範圍，故都應視為本發明的進一步實施狀況。 201141791 【圖式簡單說明】 圖一係為習知技術利用鋅-68獲取鎵-67同位素之方法的流 程示意圖。 圖二係為本發明獲取高純度銅-64同位素之方法的流程示 意圖。 圖三係顯示本發明使用不同酸度HC1淘洗液對銅-64收集 率之效果關係圖。 圖四係顯示本發明使用不同酸度HC1淘洗液對鋅-68回收 率之效果關係圖。 【主要元件符號說明】 1- 利用鋅-68獲取鎵-67同位素之方法 11〜14_步驟 2- 獲取高純度銅-64同位素之方法 21〜25-步驟 12In the present embodiment, the conditioned solution in step 22 is subjected to an HCl solution having an equivalent concentration of 9N·[ 7 201141791, and 30 ml of the cation exchange resin and the anion exchange resin are respectively passed through the cation exchange resin to activate the cation exchange resin and the anion exchange resin. A procedure for purifying the copper-64 isotope from the gallium-67 acid stream washing waste liquid was carried out. Then proceeding to step 23, the 20 ml gallium-67 acid flow washing waste liquid provided in step 21 is passed through a first column filled with a cation exchange resin, and the first tube is further washed by adding 10 ml of an equivalent concentration of 9N HCl solution. Column and collect the effluent from the first column. Then proceeding to step 24, the effluent of the first column is passed through a second column filled with an anion exchange resin, and the second column is further washed by adding 40 ml of an equivalent concentration of 9N HCl solution, and the second column is collected. The effluent from the column. Next, in step 25, an appropriate amount of an equivalent concentration of 1N or 2N of HCl solution is added to the second column, and the effluent of the second column is collected. The effluent contains high purity copper-64 isotopes. After obtaining the effluent containing the high-purity copper-64 isotope in step 25, the user can perform the step of concentrating and removing acid according to the concentration requirement to obtain high-purity copper-64 isotope of different concentrations, and the method of concentrating acid removal is used. Knowing the technology has been widely disclosed and will not be repeated here. After the stable isotope zinc-68 is irradiated by a cyclotron, the unreacted zinc-68 must be recycled. Therefore, after obtaining the effluent containing the high-purity copper-64 isotope in step 25, an appropriate amount (120 ml in the present embodiment) of water can be continuously added to the second column, and the effluent is collected to obtain zinc-68. After collecting the liquid and then concentrating it, the copper-based silver target for solid use can be recovered. Among them, the method of concentration treatment has been disclosed in the conventional technology 201141791, and will not be repeated here. The present invention also conducts an experimental test to pass the gallium-67 acid flow washing waste liquid through the cation separation and the sub-family resin (AG 50W-X2, 100~2〇〇mesh, hydrogen form) to analyze the recovery rate for copper-64. The effects of all samples were analyzed by multi-channel analyzer (MCA). The results showed that the cation exchange resin can recover more than 98% of copper·64, while gallium-67 The removal rate is over 95%. The collected liquid obtained above was further separated and purified by anion exchange resin (AG 1-Χ8, 100-200 mesh, • chloride form), and the experimental results showed that gallium-67 can be further removed. The recovery rate of copper-64 is 97%. As described above, the separation and purification of copper-64 by the cation and anion two-stage exchange resin can improve the recovery of copper-64 and the purity of the copper-64 nucleus is as high as 99.5% or more. Further, in order to obtain optimum separation conditions, the present invention simultaneously performs the influence of the different filling column specifications of the anion-cation exchange resin on the copper-64 separation. First, compare the difference between the two inner diameters of the cation exchange resin 〇.5cin and the column of lcm (the length is 15cm). Experiments show that both copper _64 flow wash rates are greater than • 99%, the inner diameter of the two columns Suitable for use. Then compare the anion exchange resin, here use three specifications of the column, respectively: (丨) inner diameter 〇 5cmX length 10cm, (2) inner diameter lcmx length l〇cm and (3) inner diameter lcmx length 15cm, analysis The results show that the copper-64 adsorption rates are (1) 98.5%, (2) 99.5%, and (3) 99.99%, respectively, which are suitable as the column specifications for anion exchange resins. Furthermore, the effect of different acidity HC1 washes on the copper-64 collection rate was compared. Figure 3 is a graph showing the effect of the use of different acidity HC1 washes on the copper-64 collection rate of the present invention. As shown in Figure 3, the copper-64 collection rates of the 201141791 HC1 panning solution with equivalent concentrations of 1N and 2N are similar, mostly concentrated in the first 20mL. Conversely, when using the equivalent concentration of 3N Ηα panning solution, copper-64 is slower. It appears and is widely distributed, resulting in a large volume of flow washing liquid, which is not conducive to the subsequent implementation of concentrated acid removal. After the stable isotope zinc-68 is irradiated by the cyclotron, the unreacted zinc-68 must be recycled for use to save the amount of zinc-68. The present invention simultaneously analyzes the effect of different acidity HC1 washes on zinc-68 recovery. Since the recovery of a substance can be reflected from its activity in the solution, Figure 4 shows the effect of the effect of the use of different acidity HC1 washes on the recovery of zinc-68. As shown in Figure 4, the recovery of zinc-68 from the HC1 wash solution at an equivalent concentration of 2 略 is slightly higher than that of the 1 Ν HC1 wash solution, but without statistical difference, showing HC1 scouring at an equivalent concentration of 1 Ν and 2 Ν. The lotion is a suitable lotion. As shown by the results of the above experiments, the elution results of the HC1 elution solution with the equivalent concentration of 1Ν or 2Ν are more ideal than the 3Ν HC1 wash solution, the copper is washed out a lot, and the zinc and gallium are adsorbed in the column. 'When the water is used as the washing liquid, a large amount of zinc is washed out. Therefore, the present invention can first use an equivalent concentration of 1 Ν or 2 Ν of the HC1 elution solution as a washing solution chromatography solution to adsorb gallium-67 and zinc-68, and wash out copper-64 to achieve the purpose of purifying nuclear species. The anion exchange resin is then continuously washed with water for recovery of zinc-68. The present invention can also be used to establish a semi-automated isotope surface production technique in a lead chamber. The yield is stable and the quality is excellent. The invention can not only save the use amount of the fixed isotope zinc-68, but also can improve the efficiency of the use of the accelerator. It can obtain two medical isotopes gallium 67 and surface]-64 at one time, and make it to the festival 10 201141791. The aim is to automate the design and reduce the radiation dose of the staff, which has great potential for application. However, the above is only an embodiment of the present invention, and the scope of the present invention is not limited thereto. It is to be understood that the scope of the present invention is not limited to the spirit and scope of the present invention, and should be considered as further implementation of the present invention. 201141791 [Simple description of the diagram] Figure 1 is a schematic diagram of a process for obtaining a gallium-67 isotope using zinc-68 by a conventional technique. Figure 2 is a schematic illustration of the process for obtaining a high purity copper-64 isotope of the present invention. Figure 3 is a graph showing the effect of the use of different acidity HC1 washes on the copper-64 collection rate of the present invention. Figure 4 is a graph showing the effect of the present invention on the recovery of zinc-68 using different acidity HC1 washes. [Explanation of main component symbols] 1- Method for obtaining gallium-67 isotope using zinc-68 11~14_Step 2- Method for obtaining high-purity copper-64 isotope 21~25-step 12