1282273 (1) 九、發明說明 【發明所屬之技術領域】 本發明係關於放射性液體的分注方法及分注裝置。 【先前技術】 以往以來，開發出：將包含以放射性核種（RI )所標 示的化合物之放射性液體投藥至體內，藉由此專用的裝置 攝影此標示化合物聚集於體內的特定部位之樣子，來診斷 疾病等的核醫學診斷法。在此診斷法，以壽命較短的放射 性核種（例如，作爲正電子釋出核種，150係具有2分 鐘、"C具有20分鐘、18F具有110分鐘之半衰期）所標 示的15〇-水或"C-甲硫胺酸或18F-FDG (脫氧葡萄糖）等 作爲放射性液體來使用。 使用於這種核醫學診斷法之放射性液體係儲存於藉由 合成裝置所合成之原容器。然後，當細分放射性液體，或 對於被實驗者投藥時，例如專利文獻1所揭示，驅動控制 注射器，由原容器分注預定量。 【專利文獻1】日本特開2002-306609號公報 【發明內容】 〔發明所欲解決之課題〕 在此，在藉由注射器僅由原容器將放射性液體分注至 分注容器之以往的方法，當放射性液體爲高濃度時，則會 產生必須分注極少量之情況。但，由於在設置於注射器的 -4 - (2) 1282273 活塞之前端的墊片會有裕度（背隙），故在分注極少量之 情況，變得無法忽視該裕度之影響，而產生無法進行正確 之分注之虞。 本發明係有鑑於上述情事而開發完成之發明，其目的 在於提供可謀求放射性液體的分注精度提昇之放射性液體 的分注方法及分注裝置。 〔用以解決課題之手段〕 本發明之放射性液體的分注方法，係藉由吸引噴出 器，由原容器將放射性液體分注至分注容器之方法。此方 法之特徵爲：由原容器抽出放射性液體之一部分，保管至 保管容器，將殘留於原容器之放射性液體稀釋後，將已被 稀釋之放射性液體分注至分注容器。 在此方法，由於由原容器抽出放射性液體之一部分， 保管至保管容器，將殘留於原容器之放射性液體稀釋，故 即使稀釋前的放射性液體爲高濃度，藉由稀釋，能夠增加 爲了獲得相同放射能量而必要之液量。因此，即使在稀釋 前，因極少量而產生不易進行利用吸引噴出氣之高精度的 分注之虞的情況，亦可藉由爲了獲得相同放射能量所必要 之液量的增加，能夠謀求放射性液體之分注精度的提昇。 此時，當原容器內的放射性液體之放射能量形成預定 値以下時，將被保管於保管容器之放射性液體的至少一部 分返回至原容器爲佳。藉此，可補充進行分注所必要之放 射性液體，而能持續進行分注作業。 -5- (3) 1282273 又，當將來自於原容器的最小取出放射能量作爲 Rm，儲存於原容器的放射性液體之濃度作爲Re，吸引噴 出器之容許最小噴出液量作爲Lm，而Rm與Re之比 (Rm/Re )作爲Z時，Z < Lm之情況，由原容器抽出放射 性液體之一部分，保管至保管容器爲佳。藉此，即使在具 有利用吸引噴出器之高精度的分注變得困難之虞爲極高的 情況，也能使分注精度確實地提昇。 又，殘留於原容器之放射性液體之稀釋前的液量L2 係作成：根據最小取出放射能量作爲Rm、容許最小噴出 液量作爲Lm、放射性液體之濃度Re、及儲存於原容器之 放射性液體的液量L!所決定之容許液量L。以下爲佳。藉 此，能夠在稀釋後將可進行利用吸引噴出器之高精度的分 注之液量的放射性液體殘留於原容器內。 本發明之放射性液體的分注裝置，其特徵爲：具備： 用來收容放射性液體之原容器；用來由原容器分注放射性 液體之分注容器；用來保管由原容器所抽出之放射性液體 的一部分之保管容器；用來進行放射性液體的吸引及噴出 之吸引噴出容器；用來供給將放射性液體稀釋的稀釋液之 稀釋液供給部；及用來在原容器、分注容器、保管容器、 吸引噴出器、及稀釋液供給部之間切換流路之流路切換手 在此裝置，能夠由原容器抽出放射性液體之一部分， 保管至保管容器，將殘留於原容器之放射性液體稀釋。因 此，即使稀釋前的放射性液體爲高濃度，藉由稀釋，能夠 -6 - (4) 1282273 增加爲了獲得相同放射能量而必要之液量。其結果，即使 在稀釋前’因極少量而產生不易進行利用吸引噴出氣之高 精度的分注之虞的情況，藉由爲了獲得相同放射能量所必 要之液量的增加，能夠謀求放射性液體之分注精度的提 昇。 〔發明效果〕 φ 若根據本發明的話，能夠謀求放射性液體的分注精度 之提昇。 【實施方式】 以下，參照圖面，說明關於本發明之實施形態。再 者，在以下的說明中，對於相同的要素賦予相同之符號， 省赂其重複的說明。 (第1實施形態） 圖1係顯示本實施形態的放射性液體的分注裝置i 〇 的結構之圖。如圖1所示，分注裝置10係具備：用來儲 存放射性液體的原液之原液瓶（原容器）1 2、可收容原液 瓶1 2並且可檢測放射線之放射線檢測器1 4。作爲放射線 檢測器1 4，能夠使用例如筒型的電離箱。以此放射線檢測 器1 4所檢測到的資料被送至後述的控制裝置1 6，使用預 先作成之放射線量一放射能量特性曲線，能由所檢測到的 放射線量，推測原液瓶1 2內之放射能量。 (5) 1282273 又，分注裝置1 〇具備重量測量器1 8及攝影裝置20 ° 重量測量器1 8可搭載原液瓶1 2，用以測量儲存於原液瓶 1 2之放射性液體的重量。作爲此重量測量器1 8 ’能夠使 用例如稱重傳感器（Loadcell )、或電子天秤。攝影裝置 2 〇係攝影原液瓶1 2，以檢測液面。作爲此攝影裝置2 0 ’ 可使用例如C C D照相機。再者，爲了容易藉由攝影裝置 2 0來對原液瓶1 2進行攝影，放射線檢測器1 4在軸方向設 φ 置未圖示的細縫爲佳。 重量測量器1 8係如上所述，可由重量檢測到原液瓶 1 2內的放射性液體之液量，又，攝影裝置20係如上所 述，可由體積（液面）檢測到原液瓶12內的放射性液體 之液量。因此，這些重量測量器1 8及攝影裝置20能夠分 別單獨構成液量檢測裝置。再者，亦可使用重量測量器18 及攝影裝置20雙方之資料來計算出液量，在該情況時， 以重量測量器1 8及攝影裝置20雙方來構成液量檢測裝 φ 置。 又，分注裝置1 0具備放射性液體之保管處所之保管 瓶（保管容器）22、用來收容起保管瓶22之保管瓶收容 部24。保管瓶收容部24係由上端開口之井型的放射線遮 蔽壁所構成的。 又，分注裝置1 〇具備放射性液體的分注處所之分注 注射器（分注容器）25。又，分注裝置1 0具備使用於進 行放射性液體的吸引及噴出之注射器（吸引噴出器）26。 注射器26係具備壓缸、與可在此壓缸內滑動之活塞。在 -8- (6) 1282273 活塞的前端，設有由橡膠等的彈性體所形成之墊 此，藉由在壓缸內按壓拉引活塞，能夠由前端口吸 性液體，或噴出放射性液體。又，分注裝置1 0具 供給稀釋了放射性液體之稀釋液的稀釋液供給部28 稀釋液，可舉出例如蒸餾水、或生理食鹽水。又， 置1 〇具備用來供給沖洗管路中的一體之沖洗氣體 氣或N2氣體）之沖洗氣體供給部30。 又，分注裝置1 〇具備用來驅動注射器26的注 動裝置32。利用以此注射器驅動裝置32使活塞 動，以進行放射性液體之吸引及噴出。 又，分注裝置10具備藍通這些原液瓶12、 22、分注注射器25、注射器26、稀釋液供給部28 氣體供給部3 0，切換流路之流路切換裝置34。流 裝置34係具有第1至第5之5個三方閥34a、3 4b、 34d、34e。第1三方閥34a的一個埠經由管36，與 12連接著。第1三方閥34a的另之外其中一個埠係 38，與沖洗氣體供給部30連接。第！三方閥34a 之其中一個埠係與第2三方閥34b的一個埠無細縫 連接。 第2三方閥34b的另外其中一個璋經由管40， 液供給部28連接。第2三方閥34b的另外其中一 與第3三方閥34e無細縫地直接連接.。第3三方閥 另外其中一個埠係與注射器26連接。第3三方閥 另外其中一個埠係與第4三方閥3 4 d的一個璋無細 片。因 入放射 備用來 。作爲 分注裝 (如空 射器驅 往復移 保管瓶 及沖洗 路切換 34c、 原液瓶 經由管 的另外 地直接 與稀釋 個埠係 3 4c的 34c的 縫地直 (7) 1282273 接連接。第4三方閥3 4 d的另外其中一個埠係經由管4 3， 與分注注射器25連接。第4三方閥34d的另外其中一個 埠與第5三方閥3 4 e無細縫地直接連接。 第5三方閥34e的另外其中一個埠與未圖示的品質檢 定部連接。又，第5三方閥34e的另外其中一個埠係經由 管42，與保管瓶22連接。 又’分注裝置1 〇係具備用來控制放射性液體的分注 φ 動作之控制裝置1 6。此控制裝置1 6係與放射線檢測器 14、重量測量器18、沖洗氣體供給部30、各三方閥34a、 34b、3 4c、3 4d、3 4e、及注射器驅動裝置32連接。利用 此控制裝置1 6之具體的控制如後所述。在此控制裝置 16，連接有用來輸入進行分注所必要之參數的輸入部44。 其次，參照圖2及圖3的流程圖，說明關於利用上述 分注裝置1 0之放射性液體的分注方法。再者，在本實施 形態，說明關於分注以18F-FDG (脫氧葡萄糖）作爲放射 φ 性液體之情況。 首先，進行分注裝置10之設置（setup )。具體而 言，將原液瓶1 2收容至放射線檢測器1 4內，搭載於重量 測量器1 8上。又，將保管瓶22收容至保管瓶收容部24。 又，將分注注射器25安裝於預定位置，在前端安裝空氣 過濾器27。然後，以管46將原液瓶12與未圖示的合成裝 置連接。又，將原液瓶1 2及沖洗氣體供給部3 0分別經由 管36、38連接到第2三方閥34b。又，將注射器26連接 到第3三方閥3 4c，並且將注射器26的活塞連接到注射器 -10- (8) 1282273 驅動裝置32。且，將保管瓶22經由管42連接到第5三方 閥3 4e。又，將分注注射器25經由管43連接到第4三方 閥 34d 〇 在此分注裝置1 〇，若結束上述安裝的話，由未圖示的 合成裝置經由管46，將FDG的原液搬送至原液瓶12後予 以儲存。其次，藉由控制裝置1 6驅動流路切換裝置34 ’ 使沖洗氣體供給部3 0與原液瓶1 2連通。然後，藉由將沖 洗氣體吹入到原液瓶1 2內，攪拌原液瓶1 2內的FDG。由 此狀態，開始將FDG分注到分注注射器25。 首先，參照圖1及圖2，經由輸入部44，將FDG的 最小取出放射能量Rm ( MBq )輸入到控制裝置1 6 (步驟 S 1 〇 )。此最小取出放射能量Rm係爲在各設施所設定之 値，爲了進行分注而由原液瓶1 2所取出之最小的放射能 量。在此，作爲一具體例，將最小取出放射能量Rm設爲 100 ( MBq )。 其次，判定最小取出放射能量Rm與儲存於原液瓶1 2 的FDG之濃度Re之比（Rm/Re )是否較注射器26之容許 最小噴出液量Lm更小（步驟S12 )。在此，如圖3所 示，控制裝置16控制放射線檢測器14與重量測量器18 及/或攝影裝置20，在每預定時間（例如1 0毫秒）測定原 液瓶12內的 FDG之放射能量 R ( MBq )與液量 L (ml )，算出FDG的放射能濃度Re (步驟S40、42、 44 )。因此，利用此被算出之放射能濃度Re進行步驟S12 之判定。再者，容許最小噴出液量Lm係爲藉由注射器 -11 - (9) 1282273 26，能夠不受裕度等的影響，以容許於液量之精度加以吸 引、噴出之最小的液量。在此，作爲一具體例，測定到 FDG的放射能量 R爲 1 0000 ( MBq )而液量 L爲 10 (ml )，則將放射能濃度Re爲1〇〇〇 ( MBq/ml )。又，將 容許最小噴出液量Lm設爲1 ( ml )。 然後，當在步驟S12的判定結果爲NO時，由於即使 不將FDG稀釋，亦可進行精度良好之分注，故可不需進 φ 行將FDG的一部分保管或稀釋，而前進至步驟S32進行 後述的分注作業。一方面，當在步驟 S 1 2的判定結果爲 YES時，前進至步驟S14。在上述的一具體例，由於比Z (Rm/Rc )爲1 ( ml )，較容許最小噴出液量Lm的1 (m 1 )更小，故前進至步驟S 1 4。 在步驟S 1 4，根據最小取出放射能量Rm與容許最小 噴出液量Lm，算出容許放射能濃度R〇 = Rm/Lm。然後’在 步驟S16，根據容許放射能濃度R。與原液瓶12內的FDG Φ 之液量L,及濃度Re，算出容許液量L^I^xRo/R。。此容許 液量L。爲當將FDG的一部分保管於原液瓶12時，可殘留 於原液瓶1 2之最大液量。當藉由稀釋液將此容許液胃L。 的FDG稀釋到原來的液量L!爲止時，能以注射器26之容 許最小噴出液量Lm取出最小取出放射能量Rm之FDG ^ & 上述一具體例，容許放射能濃度 R。形成 100 (MBq/ml )，容許液量L。形成1 ( m 1 )。 其次，藉由控制裝置1 6驅動流路切換裝置34 ’ it @ 液瓶1 2與注射器26連通。其次，藉由注射器驅動裝置3 2 -12 - (10) 1282273 驅動注射器2 6 ’開始吸引FD G (步驟S 1 8 )。其次，在驅 動注射器26後，取得殘留於原液瓶12之FDG的液量 L2，判定液量L2是否位於容許液量L。的容許誤差範圍內 (步驟S20 )。即，判定液量L2是否在容許液量1^±α以 內。此容許誤差範圍^可任意地設定’例如能設定於3 % 左右。 當在步驟 S20的判定結果爲NO時，返回至步驟 φ S 1 8，根據液量，回饋驅動注射器驅動裝置3 2使容許液量 L。與實際的液量L2之偏差變小，藉此驅動注射器26，吸 引或噴出FDG。反復進行此動作’當步驟S20的判定結果 變成YES時，前進至下一個步驟S22。藉由進行此作業， 將預定量Im-L。的FDG由原液瓶12取出至注射器26 ’使 容許液量L。的容許誤差範圍α內的FDG殘留於原液瓶12 內。作爲上述一具體例，由原液瓶12將9 ( ml )的FDG 取出至注射器26，使得1 ( ml )的容許誤差範圍α內的 _ FDG殘留於原液瓶12內。 其次，藉由控制裝置1 6驅動流路切換裝置3 4 ’使保 管瓶22與注射器26連通（步驟S22 )。然後，藉由控制 裝置16驅動注射器驅動裝置32，壓回注射器26之活塞， 將FDG噴出至保管瓶22 (步驟S24 )。進一步藉由控制 裝置1 6驅動流路切換裝置3 4，使沖洗氣體供給部3 G與注 射器2 6連通。其次，藉由從沖洗氣體供給部3 0將沖洗氣 體吸引至注射器2 6內，將殘存於流路切換裝置3 4內的 FDG與沖洗氣體吸引至注射器26。其次，藉由控制裝置 -13- (11) 1282273 16驅動流路切換裝置34，使注射器26與保管瓶22連 通。然後，藉由控制裝置1 6驅動注射器驅動裝置3 2 ’將 注射器26之活塞壓回，使FDG與沖洗氣體一同噴出至保 管瓶22。 藉此，如圖4所示，容許液量L。的FDG被儲存至原 液瓶12內，在保管瓶22形成保管了 L^L。的FDG之狀 態。在上述之一具體例，1 ( ml )的FDG被儲存於原液瓶 12內，而在保管瓶22形成9 ( ml )的FDG被保管之狀 態。 其次，算出用來稀釋殘留於原液瓶12內的FDG之稀 釋液的液量1 = 1^4。（步驟S26)。其次，藉由控制裝置 16驅動流路切換裝置34，使注射器26與稀釋液供給部28 連通。然後，將在步驟S26所算出的液量1之稀釋液吸引 至注射器26 (步驟 S28 )。在上述之一具體例，將 9 (ml )的稀釋液吸引至注射器26。 其次，藉由控制裝置1 6驅動流路切換裝置3 4，使注 射器26與原液瓶12連通。然後，藉由控制裝置16驅動 注射器驅動裝置3 2，使沖洗氣體供給部3 0與注射器2 6連 通。其次，藉由從沖洗氣體供給部將沖洗氣體吸引至注射 器2 6內，使殘存於流路切換裝置3 4內的稀釋液與沖洗氣 體一同吸引至注射器26內。其次，藉由控制裝置16驅動 流路切換裝置34，使注射器26與原液瓶12連通。然後， 藉由控制裝置1 6驅動注射器驅動裝置32，將注射器26之 活塞壓回，以將稀釋液與沖洗氣體一同噴出至原液瓶1 2。 -14- (12) 1282273 藉此，如圖5所示，在原液瓶12內形成儲存了液量 L!的已被稀釋之FDG的狀態。在上述之一具體例’在原 液瓶12內形成儲存了 10 ( ml )之已被稀釋的FDG之狀 態。此時的放射能濃度成爲1 〇〇 ( MBq/ml )。 由此狀態，開始進行對於分注注射器25之FDG的分 注作業（步驟S32 )。 首先，藉由控制裝置16/驅動流路切換裝置34,使注 φ 射器26與原液瓶12連通。然後，將期望量的FDG由原 液瓶12吸引至注射器26內。在此，在本實施形態，爲了 進行分注而被吸引至注射器26的FDG之液量經常形成注 射器26之容許最小噴出液量Lm。 其次，藉由控制裝置1 6驅動流路切換裝置34，使注 射器26與分注注射器25連通。然後，藉由控制裝置16 驅動注射器驅動裝置32，將注射器26之活塞壓回，使 FDG噴出至分注注射器25內。藉此，如圖6所示，預定 φ 量的FDG被分注至分注注射器25內。再者，在由注射器 26將FDG噴出至分注注射器25之前，亦可將稀釋液吸引 至注射器26內，在注射器26內進一步加以稀釋。 藉此，進行對於分注注射器25之FDG的分注作業。 當反復進行該分注作業，使得儲存於原液瓶12的FDG之 放射能量下降至預定量時，例如如圖7所示，未達進行下 一次分注作業所需要的放射能量時，由保管瓶22將等待 的FDG至少一部分返回至原液瓶12 首先，藉由控制裝置1 6驅動流路切換裝置34，使注 -15- (13) 1282273 射器26與保管瓶22連通。然後，將期望量的FDG由保 管瓶22吸引至注射器26。其次，藉由控制裝置1 6驅動流 路切換裝置34，使注射器26與原液瓶12連通。然後，藉 由控制裝置1 6驅動注射器驅動裝置3 2，將注射器26之活 塞壓回，如圖8所示，將FDG噴出至原液瓶12內。然 後，與上述同樣地，在原液瓶12將FDG稀釋，持續進行 對分注注射器25之分注作業。 φ 其次，說明關於本實施形態之作用及效果。 在本實施形態，由於從原液瓶1 2將FDG的一部分抽 出後保管至保管瓶22，將殘留於原液瓶12之FDG稀釋， 故即使稀釋前的FDG爲高濃度，也能夠藉由稀釋來增加 爲了獲得相同的放射能量所需要之液量。因此，即使在稀 釋前，因極少量而產生不易進行利用吸引噴出氣之高精度 的分注之虞的情況，亦可藉由爲了獲得相同放射能量所必 要之液量的增加，能夠謀求放射性液體之分注精度的提 # 昇。 特別是當來自於原容器的最小取出放射能量Rm與儲 存於原容器的放射性液體之濃度R。之比Z ( =Rm/R。）較注 射器26之容許最小噴出液量Lm更小時，由於從原液瓶1 2 將FDG的一部分抽出後保管至保管瓶22，故，即使在具 有利用吸引噴出器之高精度的分注變得困難之虞爲極高的 情況，也能使分注精度確實地提昇。除此以外之情況，藉 由不需進行原液瓶12內的FDG之稀釋、及保管瓶22之 保管’而直接進行分注作業，比起在所有之情況進行稀釋 -16- (14) 1282273 時，更可謀求分注作業之效率化。 又，由於殘留於原容器之放射性液體之稀釋前的液量 L2係作成：根據最小取出放射能量作爲Rm、容許最小噴 出液量作爲Lm、放射性液體之濃度Re、及儲存於原容器 之放射性液體的液量L 1所決定之容許液量L。，故能夠在 稀釋後將可進行利用吸引噴出器之高精度的分注之液量的 放射性液體殘留於原容器內。 φ 又，由於當原液瓶12內的FDG之放射能量形成預定 値以下時，可將被保管於保管瓶22的FDG之至少一部分 返回至原液瓶1 2，故進行分注所需要之F D G被補充，而 形成可持續進行分注作業。 (第2實施形態） 其次，說明關於本發明的第2實施形態。再者，對於 與上述第1實施形態相同之要件賦予相同的符號，省略其 • 重複說明。 第2實施形態之分注裝置1 0的結構係與上述第1實 施形態之分注裝置1 〇的結構大致相同，其分注方法不 同。 即，在上述第1實施形態，如圖2所示，最初輸入最 小取出放射能量Rm (步驟S 1 0 )，進行各種計算後，算出 殘留於原液瓶1 2之容許液量L。（步驟S 1 6 )。但，由於 會有在各設施當一旦最小取出放射能量Rm或注射器2 6之 容許最小噴出液量Lm等被設定時則無法變更之情況，故 -17- (15) 1282273 會有不需要每次進行最小取出放射能量Rm之輸入或 各種計算之情況。 因此，在本實施形態’預先由最小取出放射能量 及注射器26之容許最小噴出液量Lm，算出儲存於原 1 2內的F D G之濃度R。與容許液量L。之間的關係， 此關係，求出殘存於原液瓶1 2之液殘量L2。 表1係顯示對保管瓶22之FDG的保管前之放射 度Re、容許液量L。、及液殘量L2之關係的一例。在 之計算，FDG的液量L!設爲1 8 ( ml )，將藉由注射ί 一次可取出的放射能量之最小取出放射能量Rm設爲 (MBq )，將容許最小噴出液量Lm設爲0 · 5 ( m 1 )而 由注射器26 —次可取出的最大的放射能量之最大取 射能量設爲 450 ( MBq )，針對 0〜3 0 0 0 ( Μ B q/m 1 ) 射能濃度Re進行計算。 進行 ：Rm 液瓶 根據 能濃 表1 i 26 150 將藉 出放 之放 -18- (16) 1282273 [表1]1282273 (1) Description of the Invention [Technical Field of the Invention] The present invention relates to a dispensing method and a dispensing device for a radioactive liquid. [Prior Art] In the past, it has been developed to administer a radioactive liquid containing a compound labeled with a radioactive nucleus (RI) to a body, and to diagnose a specific part of the body by photographing the labeled compound by a dedicated device. Nuclear medicine diagnostic methods such as diseases. In this diagnostic method, a radionuclide with a short lifetime (for example, as a positron-releasing nuclear species, 150 series has 2 minutes, "C has 20 minutes, 18F has a half-life of 110 minutes), or 15〇-water or "C-methionine or 18F-FDG (deoxyglucose) is used as a radioactive liquid. The radioactive liquid system used in this nuclear medicine diagnostic method is stored in an original container synthesized by a synthesizing device. Then, when the radioactive liquid is subdivided, or when the subject is administered, for example, as disclosed in Patent Document 1, the syringe is driven to be dispensed by the original container by a predetermined amount. [Problem to be Solved by the Invention] Here, a conventional method in which a radioactive liquid is dispensed into a dispensing container by an original container by a syringe is used. When the radioactive liquid is at a high concentration, there is a case where a small amount of dispensing must be performed. However, since the gasket at the front end of the -4 - (2) 1282273 piston provided in the syringe has a margin (backlash), it becomes impossible to ignore the influence of the margin when the dispensing is extremely small. Unable to make the correct bet. The present invention has been made in view of the above circumstances, and an object of the invention is to provide a dispensing method and a dispensing device for a radioactive liquid which can improve the dispensing accuracy of a radioactive liquid. [Means for Solving the Problem] The method for dispensing a radioactive liquid of the present invention is a method of dispensing a radioactive liquid from a raw container into a dispensing container by suctioning the ejector. The method is characterized in that a part of the radioactive liquid is taken out from the original container, stored in a storage container, and the radioactive liquid remaining in the original container is diluted, and the diluted radioactive liquid is dispensed into the dispensing container. In this method, since a part of the radioactive liquid is taken out from the original container and stored in the storage container, the radioactive liquid remaining in the original container is diluted. Therefore, even if the radioactive liquid before dilution is high in concentration, it can be increased by dilution to obtain the same emission. The amount of energy necessary for energy. Therefore, even before the dilution, it is difficult to perform the high-precision dispensing by the suction and discharge gas, and the radioactive liquid can be obtained by increasing the amount of liquid necessary for obtaining the same radiation energy. The accuracy of the dispensing accuracy. At this time, when the radiation energy of the radioactive liquid in the original container is formed to be less than or equal to a predetermined value, it is preferable to return at least a part of the radioactive liquid stored in the storage container to the original container. Thereby, the radioactive liquid necessary for the dispensing can be supplemented, and the dispensing operation can be continued. -5- (3) 1282273 Further, when the minimum extracted radiant energy from the original container is taken as Rm, the concentration of the radioactive liquid stored in the original container is taken as Re, and the allowable minimum discharge amount of the suction ejector is taken as Lm, and Rm and When the ratio of Re (Rm/Re) is Z, in the case of Z < Lm, it is preferable to take out a part of the radioactive liquid from the original container and store it in a storage container. As a result, even when the high-precision dispensing using the suction ejector becomes extremely difficult, the dispensing accuracy can be surely improved. Further, the liquid amount L2 before the dilution of the radioactive liquid remaining in the original container is made to be based on the minimum extracted radiation energy as Rm, the minimum allowable discharge amount as Lm, the concentration of the radioactive liquid Re, and the radioactive liquid stored in the original container. The allowable liquid amount L determined by the liquid amount L!. The following is better. Thereby, it is possible to leave the radioactive liquid capable of performing the high-precision dispensing of the suction ejector in the original container after the dilution. A dispensing device for a radioactive liquid according to the present invention, comprising: an original container for containing a radioactive liquid; a dispensing container for dispensing a radioactive liquid from the original container; and a radioactive liquid for withdrawing the original container a part of the storage container; a suction discharge container for sucking and ejecting the radioactive liquid; a diluent supply portion for supplying the diluent for diluting the radioactive liquid; and for the original container, the dispensing container, the storage container, and the suction The flow path switching hand that switches the flow path between the ejector and the diluent supply unit is capable of extracting one part of the radioactive liquid from the original container, storing it in the storage container, and diluting the radioactive liquid remaining in the original container. Therefore, even if the radioactive liquid before dilution is at a high concentration, by dilution, it is possible to increase the amount of liquid necessary to obtain the same radiation energy by -6 - (4) 1282273. As a result, even before the dilution, it is difficult to perform the high-precision dispensing by the suction and discharge gas, and it is possible to obtain a radioactive liquid by increasing the amount of liquid necessary for obtaining the same radiation energy. Increased dispensing accuracy. [Effect of the Invention] φ According to the present invention, it is possible to improve the dispensing accuracy of the radioactive liquid. [Embodiment] Hereinafter, embodiments of the present invention will be described with reference to the drawings. In the following description, the same elements are denoted by the same reference numerals, and the description thereof will be repeated. (First Embodiment) Fig. 1 is a view showing the configuration of a dispensing device i 放射性 of a radioactive liquid according to the present embodiment. As shown in Fig. 1, the dispensing device 10 includes a raw liquid bottle (original container) for storing a stock solution of a radioactive liquid, and a radiation detector 14 that can accommodate the raw liquid bottle 12 and can detect radiation. As the radiation detector 14, for example, a cylindrical ionization chamber can be used. The data detected by the radiation detector 14 is sent to a control device 16 described later, and the radiation amount-radiation energy characteristic curve prepared in advance can be used to estimate the amount of radiation detected in the original liquid bottle 1 2 . Radiation energy. (5) 1282273 Further, the dispensing device 1 〇 is provided with a weight measuring device 18 and a photographing device 20 °. The weight measuring device 18 can be equipped with a raw liquid bottle 12 for measuring the weight of the radioactive liquid stored in the original liquid bottle 12. As the weight measurer 18', for example, a load cell or an electronic balance can be used. Photographic device 2 Tethered photographic liquid bottle 1 2 to detect the liquid level. As the photographing device 2 0 ', for example, a C C D camera can be used. Further, in order to easily photograph the original liquid bottle 12 by the photographing device 20, it is preferable that the radiation detector 14 is provided with a slit (not shown) in the axial direction. The weight measuring device 18 is capable of detecting the liquid amount of the radioactive liquid in the original liquid bottle 12 by the weight as described above, and the photographing device 20 detects the radioactivity in the original liquid bottle 12 from the volume (liquid level) as described above. The amount of liquid in the liquid. Therefore, the weight measuring device 18 and the photographing device 20 can separately constitute the liquid amount detecting device. Further, the amount of liquid can be calculated using the data of both the weight measuring device 18 and the photographing device 20. In this case, the liquid amount detecting device φ is configured by both the weight measuring device 18 and the photographing device 20. Further, the dispensing device 10 includes a storage bottle (storage container) 22 for storing a radioactive liquid, and a storage bottle accommodating portion 24 for accommodating the storage bottle 22. The storage bottle accommodating portion 24 is constituted by a well-type radiation shielding wall having an open upper end. Further, the dispensing device 1 is provided with a dispensing syringe (dispensing container) 25 for dispensing a radioactive liquid. Further, the dispensing device 10 includes a syringe (suction ejector) 26 for performing suction and ejection of the radioactive liquid. The syringe 26 is provided with a pressure cylinder and a piston that can slide in the cylinder. At the front end of the piston of -8-(6) 1282273, a pad made of an elastic body such as rubber is provided. By pressing the pull-out piston in the cylinder, the liquid can be sucked from the front port or the radioactive liquid can be ejected. Further, the dispensing device 10 has a diluent supply unit 28 diluted with a diluent for diluting the radioactive liquid, and examples thereof include distilled water or physiological saline. Further, a flushing gas supply unit 30 for supplying an integrated flushing gas or N2 gas in the flushing line is provided. Further, the dispensing device 1 〇 is provided with a stopper 32 for driving the syringe 26. The piston drive unit 32 is used to move the piston to perform suction and ejection of the radioactive liquid. Further, the dispensing device 10 includes the original liquid bottles 12 and 22, the dispensing syringe 25, the syringe 26, and the diluent supply unit 28 gas supply unit 30, and switches the flow path switching device 34 of the flow path. The flow device 34 has five first-to-five three-way valves 34a, 34b, 34d, and 34e. One turn of the first trim valve 34a is connected to 12 via the pipe 36. One of the other tethers 38 of the first trim valve 34a is connected to the flushing gas supply unit 30. The first! One of the three-way valves 34a is connected to one of the second three-way valves 34b without a slit. The other one of the second trim valve 34b is connected via the tube 40 and the liquid supply unit 28. The other of the second trim valve 34b is directly connected to the third trim valve 34e without a slit. The third trim valve is also connected to the syringe 26. The third trim valve is one of the other lanthanum and the fourth trim valve. Because of the radiation into the spare. As a dispensing device (such as an air-jet reciprocating storage bottle and flushing path switch 34c, the original liquid bottle is directly connected to the grounding line (7) 1282273 of the 34c of the dilute system 3 4c via the tube. The other one of the three-way valve 34 d is connected to the dispensing syringe 25 via the tube 43. The other one of the third three-way valve 34d is directly connected to the fifth three-way valve 34 4 without a slit. The other one of the three-way valve 34e is connected to a quality detecting unit (not shown). Further, one of the other three-way valves 34e is connected to the storage bottle 22 via the tube 42. Further, the dispensing device 1 is provided with A control device 16 for controlling the dispensing of the radioactive liquid φ. The control device 16 is connected to the radiation detector 14, the weight measuring device 18, the flushing gas supply unit 30, and the three-way valves 34a, 34b, 3 4c, 3 4d, 3 4e, and the syringe driving device 32 are connected. The specific control by the control device 16 will be described later. The control device 16 is connected to the input unit 44 for inputting parameters necessary for dispensing. , refer to the flow of Figure 2 and Figure 3 The dispensing method of the radioactive liquid by the above-described dispensing device 10 will be described. In the present embodiment, the case where 18F-FDG (deoxyglucose) is used as the radiation φ liquid will be described. Specifically, the stock bottle 12 is housed in the radiation detector 14 and mounted on the weight measuring device 18. The storage bottle 22 is housed in the storage bottle accommodating portion 24. Further, the dispensing syringe 25 is attached to a predetermined position, and the air filter 27 is attached to the tip end. Then, the original liquid bottle 12 is connected to a synthesizing device (not shown) by a tube 46. Further, the original liquid bottle 12 and the flushing gas supply unit are connected. 30 is connected to the second trim valve 34b via tubes 36, 38, respectively. Again, the syringe 26 is connected to the third trim valve 34c and the piston of the syringe 26 is connected to the syringe-10-(8) 1282273 drive unit 32. Further, the storage bottle 22 is connected to the fifth trim valve 34e via the tube 42. Further, the dispensing syringe 25 is connected to the fourth trim valve 34d via the tube 43 at the dispensing device 1 〇, and if the above installation is completed, Synthetic equipment not shown The stock solution of the FDG is transferred to the original liquid bottle 12 via the tube 46 and stored. Next, the flow rate switching device 34' is driven by the control device 16 to connect the flushing gas supply unit 30 to the original liquid bottle 12. Then, The flushing gas is blown into the original liquid bottle 1 2, and the FDG in the original liquid bottle 12 is stirred. In this state, the FDG is started to be dispensed into the dispensing syringe 25. First, referring to Figs. 1 and 2, via the input portion 44, The minimum extracted radiant energy Rm (MBq) of the FDG is input to the control device 16 (step S1 〇). The minimum extracted radiant energy Rm is the minimum amount of radiant energy taken out from the original liquid bottle 12 for dispensing. Here, as a specific example, the minimum extracted radiation energy Rm is set to 100 (MBq). Next, it is judged whether or not the ratio (Rm/Re) of the minimum extracted radiant energy Rm to the concentration Re of the FDG stored in the original liquid bottle 12 is smaller than the allowable minimum ejection liquid amount Lm of the syringe 26 (step S12). Here, as shown in FIG. 3, the control device 16 controls the radiation detector 14 and the weight measuring device 18 and/or the photographing device 20 to measure the radiation energy R of the FDG in the original liquid bottle 12 every predetermined time (for example, 10 ms). (MBq) and the liquid amount L (ml), the radioactivity concentration Re of the FDG is calculated (steps S40, 42, 44). Therefore, the determination of step S12 is performed using the calculated radiation energy concentration Re. In addition, the minimum allowable discharge amount Lm is the smallest amount of liquid that can be sucked and discharged by the accuracy of the liquid amount without being affected by the margin or the like by the syringe -11 - (9) 1282273 26 . Here, as a specific example, when the radiation energy R of the FDG is measured to be 1 0000 (MBq) and the liquid amount L is 10 (ml), the radioactivity concentration Re is 1 〇〇〇 (MBq/ml). Further, the minimum allowable discharge amount Lm is set to 1 (ml). Then, when the result of the determination in step S12 is NO, even if the FDG is not diluted, the dispensing with high precision can be performed. Therefore, it is possible to store or dilute a part of the FDG without entering the φ line, and proceed to step S32 to be described later. The dispensing operation. On the other hand, when the decision result in the step S12 is YES, the process proceeds to a step S14. In the above specific example, since the ratio Z (Rm/Rc) is 1 (ml) and the allowable minimum discharge amount Lm is smaller than 1 (m 1 ), the process proceeds to step S14. In step S14, the allowable radiation energy concentration R? = Rm/Lm is calculated from the minimum extracted radiation energy Rm and the allowable minimum discharge liquid amount Lm. Then 'at step S16, according to the allowable radiation energy concentration R. The allowable liquid amount L^I^xRo/R is calculated from the liquid amount L of the FDG Φ in the original liquid bottle 12 and the concentration Re. . This allowable amount of liquid L. In order to store a part of the FDG in the original liquid bottle 12, the maximum liquid amount remaining in the original liquid bottle 12 can be left. This allows the stomach L to be allowed by the diluent. When the FDG is diluted to the original liquid amount L!, the FDG of the minimum extracted radiation energy Rm can be taken out by the minimum discharge amount Lm of the syringe 26, and the above specific example is allowed to have the radioactive energy concentration R. Form 100 (MBq/ml) and allow the amount of liquid L. Form 1 ( m 1 ). Next, the flow path switching device 34'' it @ liquid bottle 12 is driven by the control unit 16 to communicate with the syringe 26. Next, the syringe 2 6 ' is driven to start attracting FD G by the syringe driving device 3 2 -12 - (10) 1282273 (step S 18). Next, after the syringe 26 is driven, the liquid amount L2 of the FDG remaining in the original liquid bottle 12 is obtained, and it is determined whether or not the liquid amount L2 is located in the allowable liquid amount L. Within the tolerance range (step S20). That is, it is determined whether or not the liquid amount L2 is within the allowable liquid amount 1^±α. This allowable error range ^ can be arbitrarily set, for example, can be set to about 3%. When the result of the determination in step S20 is NO, the flow returns to step φ S 1 8 to feed back the syringe driving device 3 2 to allow the liquid amount L according to the amount of liquid. The deviation from the actual liquid amount L2 becomes small, whereby the syringe 26 is driven to suck or discharge the FDG. This operation is repeated. When the result of the determination in step S20 becomes YES, the process proceeds to the next step S22. By performing this operation, a predetermined amount of Im-L will be used. The FDG is taken out from the original liquid bottle 12 to the syringe 26' to allow the liquid amount L. The FDG in the allowable error range α remains in the original liquid bottle 12. As a specific example described above, 9 (ml) of FDG is taken out from the original solution bottle 12 to the syringe 26 so that _ FDG in the allowable error range α of 1 (ml) remains in the original solution bottle 12. Next, the control unit 16 drives the flow path switching device 3 4 ' to connect the vial 22 to the syringe 26 (step S22). Then, the syringe driving device 32 is driven by the control device 16, and the piston of the syringe 26 is pressed back to eject the FDG to the storage bottle 22 (step S24). Further, the flow rate switching device 34 is driven by the control unit 16 to connect the flushing gas supply unit 3 G with the injector 26. Then, the flushing gas is sucked into the syringe 26 from the flushing gas supply unit 30, and the FDG and the flushing gas remaining in the flow path switching device 34 are sucked into the syringe 26. Next, the flow path switching device 34 is driven by the control device -13-(11) 1282273 16 to connect the syringe 26 to the storage bottle 22. Then, the plunger of the syringe 26 is pressed back by the control device 16 to drive the syringe driving device 3 2 ', and the FDG is ejected together with the flushing gas to the vial 22. Thereby, as shown in FIG. 4, the liquid amount L is allowed. The FDG is stored in the original liquid bottle 12, and the storage bottle 22 is formed to store L^L. The state of the FDG. In one of the above specific examples, 1 (ml) of FDG is stored in the original liquid bottle 12, and 9 (ml) of FDG is stored in the storage bottle 22. Next, the amount of liquid 1 = 1^4 used to dilute the dilution liquid of the FDG remaining in the original liquid bottle 12 was calculated. (Step S26). Next, the flow path switching device 34 is driven by the control device 16, and the syringe 26 is communicated with the diluent supply portion 28. Then, the dilution liquid of the liquid amount 1 calculated in step S26 is sucked to the syringe 26 (step S28). In one of the above specific examples, 9 (ml) of the diluted solution is sucked into the syringe 26. Next, the flow path switching device 34 is driven by the control unit 16 to connect the injector 26 to the original liquid bottle 12. Then, the syringe driving device 3 2 is driven by the control unit 16 to connect the flushing gas supply unit 30 to the syringe 26. Then, the flushing gas is sucked into the syringe 26 from the flushing gas supply unit, and the diluent remaining in the flow path switching device 34 is sucked into the syringe 26 together with the flushing gas. Next, the flow path switching device 34 is driven by the control unit 16 to connect the syringe 26 to the original liquid bottle 12. Then, the syringe driving device 32 is driven by the control unit 16, and the piston of the syringe 26 is pressed back to eject the diluent together with the flushing gas to the original liquid bottle 12. -14- (12) 1282273 Thereby, as shown in Fig. 5, the state of the diluted FDG in which the liquid amount L! is stored is formed in the original liquid bottle 12. In one of the above specific examples, 10 (ml) of the diluted FDG was stored in the original liquid bottle 12. The concentration of radioactivity at this time was 1 〇〇 (MBq/ml). In this state, the dispensing operation for the FDG of the dispensing syringe 25 is started (step S32). First, the injection device 26 is driven to communicate with the original liquid bottle 12 by the control device 16 / drive flow switching device 34. The desired amount of FDG is then drawn from the original vial 12 into the syringe 26. Here, in the present embodiment, the liquid amount of the FDG sucked to the syringe 26 for dispensing is often formed as the allowable minimum discharge liquid amount Lm of the syringe 26. Next, the flow path switching device 34 is driven by the control unit 16 to connect the injector 26 to the dispensing syringe 25. Then, the syringe driving device 32 is driven by the control device 16, and the piston of the syringe 26 is pressed back to eject the FDG into the dispensing syringe 25. Thereby, as shown in Fig. 6, the FDG of a predetermined amount of φ is dispensed into the dispensing syringe 25. Further, before the FDG is ejected from the syringe 26 to the dispensing syringe 25, the diluent may be sucked into the syringe 26 and further diluted in the syringe 26. Thereby, the dispensing operation for the FDG of the dispensing syringe 25 is performed. When the dispensing operation is repeated such that the radiant energy of the FDG stored in the original liquid bottle 12 is reduced to a predetermined amount, for example, as shown in FIG. 7, when the radiant energy required for the next dispensing operation is not reached, the storage bottle is used. 22 Returning at least a portion of the waiting FDG to the original liquid bottle 12 First, the flow path switching device 34 is driven by the control device 16 to connect the -15-(13) 1282273 ejector 26 to the storage bottle 22. The desired amount of FDG is then drawn from the vial 22 to the syringe 26. Next, the flow switching device 34 is driven by the control unit 16 to connect the syringe 26 to the original solution bottle 12. Then, the syringe driving device 3 2 is driven by the control unit 16, and the piston of the syringe 26 is pressed back, and as shown in Fig. 8, the FDG is ejected into the original liquid bottle 12. Then, in the same manner as described above, the FDG is diluted in the original liquid bottle 12, and the dispensing operation for the dispensing syringe 25 is continued. φ Next, the action and effect of the present embodiment will be described. In the present embodiment, a part of the FDG is taken out from the original liquid bottle 12 and stored in the storage bottle 22, and the FDG remaining in the original liquid bottle 12 is diluted. Therefore, even if the FDG before dilution is high, it can be increased by dilution. The amount of liquid required to obtain the same amount of radiant energy. Therefore, even before the dilution, it is difficult to perform the high-precision dispensing by the suction and discharge gas, and the radioactive liquid can be obtained by increasing the amount of liquid necessary for obtaining the same radiation energy. The accuracy of the dispensing accuracy is #升. In particular, the minimum extracted radiant energy Rm from the original container and the concentration R of the radioactive liquid stored in the original container. The ratio Z (=Rm/R.) is smaller than the allowable minimum discharge liquid amount Lm of the syringe 26, and a part of the FDG is taken out from the original liquid bottle 1 2 and stored in the storage bottle 22, so that even if the suction discharge device is used The high-precision dispensing becomes difficult, and the dispensing accuracy is surely improved. In other cases, the dispensing operation is performed directly without the need to perform the dilution of the FDG in the original liquid bottle 12 and the storage of the storage bottle 22, and the dilution is performed in all cases - 16 - (14) 1282273 It is also possible to improve the efficiency of the dispensing operation. Further, the amount of liquid L2 before dilution of the radioactive liquid remaining in the original container is made to be based on the minimum extracted radiation energy as Rm, the minimum allowable discharge amount as Lm, the concentration of the radioactive liquid Re, and the radioactive liquid stored in the original container. The allowable liquid amount L determined by the liquid amount L 1 . Therefore, it is possible to leave the radioactive liquid capable of performing the high-precision dispensing of the suction ejector in the original container after the dilution. φ Further, when the radiation energy of the FDG in the original liquid bottle 12 is formed to be less than or equal to a predetermined value, at least a part of the FDG stored in the storage bottle 22 can be returned to the original liquid bottle 12, so that the FDG required for dispensing is supplemented. And form a sustainable dispensing operation. (Second Embodiment) Next, a second embodiment of the present invention will be described. The same components as those in the above-described first embodiment are denoted by the same reference numerals, and the description thereof will not be repeated. The configuration of the dispensing device 10 of the second embodiment is substantially the same as that of the dispensing device 1 of the first embodiment described above, and the dispensing method is different. In the first embodiment, as shown in Fig. 2, the minimum extracted radiation energy Rm is first input (step S1 0), and after various calculations, the allowable liquid amount L remaining in the original liquid bottle 12 is calculated. (Step S16). However, since there is a case where the minimum allowable discharge amount Rm or the allowable minimum discharge amount Lm of the syringe 26 is set at each facility, the -17-(15) 1282273 may not be required each time. The case where the input of the minimum extraction radiation energy Rm or various calculations is performed is performed. Therefore, in the present embodiment, the concentration R of the F D G stored in the original 12 is calculated by the minimum extraction of the radiation energy and the allowable minimum discharge amount Lm of the syringe 26 in advance. With the allowable liquid amount L. Relationship between the relationship, and the residual amount L2 remaining in the original liquid bottle 1 2 is obtained. Table 1 shows the radiation Re and the allowable liquid amount L before storage of the FDG of the storage bottle 22. And an example of the relationship between the liquid residue amount L2. In the calculation, the liquid volume L! of the FDG is set to 18 (ml), and the minimum extracted radiant energy Rm of the radiant energy that can be taken out by the injection ί is set to (MBq), and the minimum allowable discharge amount Lm is set to 0 · 5 ( m 1 ) and the maximum emission energy of the maximum radiant energy that can be taken out by the syringe 26 is set to 450 (MBq) for the energy concentration of 0~3 0 0 0 ( Μ B q/m 1 ) Re performs calculations. Carry out: Rm liquid bottle according to energy concentration Table 1 i 26 150 will be released and put out -18- (16) 1282273 [Table 1]
等待前 等待後 濃度R〇 最小噴出液量 容許液量L。 殘液量l2 吸事後濃度 最大噴出液量 最小噴出液量 3000 0.05 1.8 1.5 250.0 1.8 0.60 2900 0.05 1.9 1.5 241.7 1.9 0.62 2800 0.05 1.9 1.5 233.3 1.9 0.64 2700 0.06 2.0 1.5 225.0 2.0 0.67 2600 0.06 2.1 1.5 216.7 2.1 0.69 2500 0.06 2.2 1.5 208.3 2.2 0.72 2400 0.06 2.3 1.5 200.0 2.3 0.75 2300 0.07 2.3 1.5 191.7 2.3 0.78 2200 0.07 2.5 1.5 183.3 2.5 0.82 2100 0.07 2.6 1.5 175.0 2.6 0.86 2000 0.08 2.7 1.5 166.7 2.7 0.90 1900 0.08 2.8 1.5 158.3 2.8 0.95 1800 0.08 3.0 1.5 150.0 3.0 1.00 1700 0.09 3.2 3.0 283.3 1.6 0.53 1600 0.09 3.4 3.0 266.7 1.7 0.56 1500 0.10 3.6 3.0 250.0 1.8 0.60 1400 0.11 3.9 3.0 233.3 1.9 0.64 1300 0.12 4.2 3.0 216.7 2.1 0.69 1200 0.13 4.5 3.0 200.0 2.3 0.75 1100 0.14 4.9 3.0 183.3 2.5 0.82 1000 0.15 5.4 3.0 166.7 2.7 0.90 900 0.17 6.0 3.0 150.0 3.0 1.00 800 0.19 6.8 6.0 266.7 1.7 0.56 700 0.21 7.7 6.0 233.3 1.9 0.64 600 0.25 9.0 6.0 200.0 2.3 0.75 500 0.30 10.8 6.0 166.7 2.7 0.90 400 0.38 13.5 6.0 133.3 3.4 1.13 300 0.50 18.0 18.0 - - 200 0.75 18.0 18.0 • • 100 1.50 18.0 18.0 • • • 〇 * 1 * 2 * 2 * 1 :稀釋成總液量成爲1 8 m 1 *2 :所使用之取出注射器的尺寸爲5ml或10ml -19- (17) 1282273 如表1的第1欄及第2欄所示，可得知，當將FDG 保管於保管瓶22之前的放射能濃度Re超過容許放射能濃 度R。之3 00 ( MBq/ml )時，則爲了取出最小取出放射能 量Rm之150 ( MBq )，需要使最小噴出液量小於容許最小 噴出液量Lm之0.5 ( ml )。因此，在此情況，需要將]fdG 的一部分保管於保管瓶22，而將其餘予以稀釋。在此情 況，由於殘留於原液瓶1 2之F D G的液殘量L 2需作成容許 液量L。以下，故由Lfl^xRe/Re之關係式，首先算出容許 液量L。。如此所算出之容許液量L。記載於表1的第3 在本實施形態，如表1的第4欄所示，在放射能濃度 Rc爲1 800 ( MBq/ml )以上，將殘液量 l2設爲ι.5 (ml)，在放射能濃度Rc爲900 ( MBq/ml)以上而至 1800(MBq/ml)爲止，將殘液量L2設爲3.0(ml)，在 放射能濃度Re爲超過300 ( MBq/ml )設爲1.5 ( ml )而至 900 ( MBq/ml )設爲 爲止，將殘液量 L2設爲 6.0 ( ml)，而在放射能濃度R。爲300 ( MBq/ml )以下， 則殘液量L2設爲18 ( ml )。 如此所決定之殘液量L2係如表1的第3及第4搁所 示，由於較所有之容許液量L。低，故即使在稀釋至原來 的液量18 ( ml )，將最小取出放射能量Rm之15〇 (MBq )的FDG取出之情況，也可如表1的第7欄所示， 最小噴出液量不會低於注射器2 6的容許最小噴出液量 L· m 之 0.5 ( ml )。 -20- (18) 1282273 再者，在表1的第5欄所指之稀釋後濃度，係指將殘 液量L2之FDG稀釋至原來的液量18 ( ml )爲止時之放射 能濃度。又，在表1的第6欄所指之最大噴出液量，係指 取出最大取出放射能量之45 0 ( MBq )的FDG時所需之噴 出量。 由上述結果，將儲存於原液瓶12內之FDG的濃度 Rc、與等待保管於原液瓶12之等待液量Lt之關係，顯示 φ 於表2。本實施形態之分注裝置1 0係將如表2所示之表預 先記憶於控制裝置1 6的記憶體。 [表2] 濃度Rc 等待液量L t 1800〜3000 16.5 900〜1799 15 3 0 1 〜8 9 9 12 0 〜300 0 其次，參照圖9及圖10之流程，說明關於本實施形 態之分注方法。 首先，與第〗實施形態同樣地進行分注裝置〗〇之安 裝。若上述安裝結束的話，經由管46由未圖示的合成裝 置，將FDG的原液搬送至原液瓶12加以儲存。其次，藉 由控制裝置1 6驅動流路切換裝置34，使沖洗氣體供給部 3 〇與原液瓶1 2連通。然後，藉由將沖洗氣體吹入到原液 瓶12內，以將原液瓶12內之FDG予以攪拌。由此狀 (19) 1282273 態，開始進行FDG對於分注注射器25之分注 首先，根據儲存於原液瓶12之FDG的濃 等待保管於保管瓶22之FDG的等待液| S 1〇〇 )。在此，如參照圖3所進行的說明般， 置1 6係控制放射線檢測器1 4、與重量測量器 影裝置20，在每預定時間（例如1 〇微秒）測 內的FDG之放射能量R(MBq)與液量L( φ FDG的放射能濃度Rc (圖3的步驟S40、S42 利用此被算出之放射能濃度。又，在進行決 Lt之際，利用顯示預先求出之濃度與等待丨 係之表2的表格。 其次，判定原液瓶12內的FDG之液量L】 液量Lt小（步驟S102 )。當在步驟S102的 YES時，前進至步驟 S104，發出液量不足之 分注作業。在此情況，藉由作業者的判斷’稀 φ 內之FDG，增加了液量後，由最初開始進行分 方面，當在步驟S1 02之判定結果爲NO時’ S 1 06 〇 在步驟S106，將等待於保管瓶22之等存 FDG之放射能濃度Rts作爲Re加以記憶。其 S108，記憶將記憶放射能濃度Rts時之時刻Tts 其次，使在上述步驟S 1 0 0所決定之等待 FDG等待保管至保管瓶22 (步驟S1 10 )。再 動作，亦可根據等待液量Lt，藉由注射器驅動 度Re，決定 I Lt (步驟 由於控制裝 18及/或攝 量原液瓶1 2 ml)，算出 、S44 )，故 :定等待液量 夜量Lt的關 是否較等待 1判定結果爲 警告，結束 釋原液瓶1 2 注作業。一 前進至步驟 f液量Lt的 次，在步驟 〇 Μ液量Lt的 者，在等待 裝置3 2僅 -22- (20) 1282273 將注射器26驅動，亦可與第1實施形態同樣地’算出殘 留於原液瓶12之FDG的殘液量L2，藉由根據液面之回饋 控制，來驅動控制注射器26，使液量L2位於容許誤差範 圍內。 然後，與第1實施形態同樣地，在步驟S 1 12，將原 液瓶12內的FDG稀釋至原來的液量，在步驟S114’將已 被稀釋的FDG分注至分注注射器25。如此，進行FDG對 φ 分注注射器25之分注作業。當反復進行該分注作業’使 得儲存於原液瓶12之FDG的液量L下降到較預定量低 時，在此爲較最小殘量Lx低時，由保管瓶22進行FDG對 原液瓶1 2之返回作業。此最小殘量Lx可任意地設定。 在此，參照圖1〇，說明關於由保管瓶22將FDG對原 液瓶1 2之返回作業。 首先，在步驟S200，判定儲存於原液瓶12之FDG的 液量L是否較最小殘量Lx小。當步驟S200之判定結果爲 φ YES時，前進至步驟S202，根據下述方程式算出儲存於 保管瓶22內的FDG之現在的放射能濃度Rtn。Waiting before waiting Waiting concentration R〇 Minimum discharge amount Allowable liquid amount L. Residual liquid amount l2 After suction, the maximum concentration of the ejected liquid, the minimum amount of ejected liquid 3000 0.05 1.8 1.5 250.0 1.8 0.60 2900 0.05 1.9 1.5 241.7 1.9 0.62 2800 0.05 1.9 1.5 233.3 1.9 0.64 2700 0.06 2.0 1.5 225.0 2.0 0.67 2600 0.06 2.1 1.5 216.7 2.1 0.69 2500 0.06 2.2 1.5 208.3 2.2 0.72 2400 0.06 2.3 1.5 200.0 2.3 0.75 2300 0.07 2.3 1.5 191.7 2.3 0.78 2200 0.07 2.5 1.5 183.3 2.5 0.82 2100 0.07 2.6 1.5 175.0 2.6 0.86 2000 0.08 2.7 1.5 166.7 2.7 0.90 1900 0.08 2.8 1.5 158.3 2.8 0.95 1800 0.08 3.0 1.5 150.0 3.0 1.00 1700 0.09 3.2 3.0 283.3 1.6 0.53 1600 0.09 3.4 3.0 266.7 1.7 0.56 1500 0.10 3.6 3.0 250.0 1.8 0.60 1400 0.11 3.9 3.0 233.3 1.9 0.64 1300 0.12 4.2 3.0 216.7 2.1 0.69 1200 0.13 4.5 3.0 200.0 2.3 0.75 1100 0.14 4.9 3.0 183.3 2.5 0.82 1000 0.15 5.4 3.0 166.7 2.7 0.90 900 0.17 6.0 3.0 150.0 3.0 1.00 800 0.19 6.8 6.0 266.7 1.7 0.56 700 0.21 7.7 6.0 233.3 1.9 0.64 600 0.25 9.0 6.0 200.0 2.3 0.75 500 0.30 10.8 6.0 166.7 2.7 0.90 400 0.38 13.5 6.0 133.3 3.4 1.13 300 0.50 18.0 18.0 - - 200 0.75 18.0 18.0 • • 100 1.50 18.0 18.0 • • • 〇* 1 * 2 * 2 * 1 : Dilute to a total volume of 1 8 m 1 *2 : The size of the syringe to be used is 5ml or 10ml - 19-(17) 1282273 As shown in the first column and the second column of Table 1, it is understood that the radioactivity concentration Re before the storage of the FDG in the storage bottle 22 exceeds the allowable radiation energy concentration R. In the case of 3 00 (MBq/ml), in order to take out the minimum extracted radioactivity Rm of 150 (MBq), it is necessary to make the minimum discharge amount smaller than 0.5 (ml) of the allowable minimum discharge amount Lm. Therefore, in this case, it is necessary to store a part of [fdG] in the storage bottle 22, and to dilute the rest. In this case, the liquid amount L 2 of the F D G remaining in the original liquid bottle 12 is required to be the allowable liquid amount L. Hereinafter, the allowable liquid amount L is first calculated from the relational expression of Lfl^xRe/Re. . The allowable liquid amount L thus calculated. In the third embodiment of Table 1, as shown in the fourth column of Table 1, the radioactivity concentration Rc is 1 800 (MBq/ml) or more, and the residual liquid amount l2 is set to ι.5 (ml). When the radioactivity concentration Rc is 900 (MBq/ml) or more and 1800 (MBq/ml), the residual liquid amount L2 is 3.0 (ml), and the radioactive energy concentration Re is more than 300 (MBq/ml). From 1.5 (ml) to 900 (MBq/ml), the residual liquid amount L2 is set to 6.0 (ml), and the radioactive energy concentration R is set. When it is 300 (MBq/ml) or less, the residual liquid amount L2 is set to 18 (ml). The amount of residual liquid L2 thus determined is shown in the third and fourth places of Table 1, because of the allowable liquid amount L. It is low, so even if it is diluted to the original liquid volume of 18 (ml), the FDG with a minimum of 15 〇 (MBq) of the radiant energy Rm can be taken out, as shown in the seventh column of Table 1, the minimum discharge amount. It is not lower than 0.5 (ml) of the allowable minimum discharge amount L·m of the syringe 26. -20- (18) 1282273 Further, the post-dilution concentration referred to in the fifth column of Table 1 means the radioactive energy concentration when the FDG of the residual liquid amount L2 is diluted to the original liquid amount of 18 (ml). Further, the maximum discharge amount referred to in the sixth column of Table 1 means the discharge amount required to take out the FDG of 45 0 (MBq) which is the maximum extraction of the radiation energy. From the above results, the relationship between the concentration Rc of the FDG stored in the original liquid bottle 12 and the waiting liquid amount Lt waiting to be stored in the original liquid bottle 12 is shown in Table 2. The dispensing device 10 of the present embodiment stores the table shown in Table 2 in advance in the memory of the control device 16. [Table 2] Concentration Rc Waiting liquid amount L t 1800 to 3000 16.5 900 to 1799 15 3 0 1 to 8 9 9 12 0 to 300 0 Next, with reference to the flow of Figs. 9 and 10, the dispensing of the present embodiment will be described. method. First, the dispensing device is mounted in the same manner as in the first embodiment. When the above-described mounting is completed, the raw material of the FDG is transferred to the original liquid bottle 12 via the tube 46 by a synthesizing device (not shown) and stored. Next, the flow path switching device 34 is driven by the control device 16 to allow the flushing gas supply unit 3 to communicate with the original liquid bottle 12. Then, the FDG in the original liquid bottle 12 is stirred by blowing a flushing gas into the original liquid bottle 12. In the state of (19) 1282273, the dispensing of the FDG into the dispensing syringe 25 is started. First, the waiting liquid (S 1 〇〇 ) of the FDG stored in the storage bottle 22 is stored in accordance with the concentration of the FDG stored in the original liquid bottle 12. Here, as described with reference to FIG. 3, the radiation energy of the FDG measured by the radiation detector 14 and the weight measuring device 20 every predetermined time (for example, 1 〇 microsecond) is set. R (MBq) and the liquid amount L (radiation energy concentration Rc of φ FDG (the radioactive energy concentration calculated by the steps S40 and S42 of Fig. 3), and the concentration obtained in advance by the display is performed when the Lt is calculated. Waiting for the table of Table 2 of the system. Next, it is determined that the liquid amount L of the FDG in the original liquid bottle 12 is small (step S102). When YES in step S102, the process proceeds to step S104, and the liquid amount is insufficient. In this case, by the operator's judgment, the FDG in the thin φ increases the amount of liquid, and the division is started from the beginning, and when the result of the determination in step S102 is NO, 'S 1 06 〇 In step S106, the radioactive energy concentration Rts of the stored FDG waiting for the storage bottle 22 is stored as Re. In S108, the time Tts at which the radioactive energy concentration Rts is stored is stored next, and is determined in the above step S1 0 0. Waiting for the FDG to wait for storage in the storage bottle 22 (step S1 10). According to the waiting liquid amount Lt, I Lt can be determined by the syringe driving degree Re (steps are controlled by the control device 18 and/or the liquid sample bottle 12 ml), and S44) is calculated, so that the waiting liquid amount is Lt. Whether the check is a warning or not, the end of the test result is a warning, and the end of the liquid bottle 1 2 is injected. When the process proceeds to step f, the amount of liquid Lt, at the step of the liquid amount Lt, while waiting for the device 3 2 only -22- (20) 1282273 The syringe 26 is driven, and the residual liquid amount L2 of the FDG remaining in the original liquid bottle 12 can be calculated in the same manner as in the first embodiment, and the control syringe 26 can be driven to control the liquid according to the liquid level feedback control. The amount L2 is within the allowable error range. Then, in the same manner as in the first embodiment, the FDG in the original liquid bottle 12 is diluted to the original liquid amount in step S112, and the diluted FDG is dispensed in step S114'. To dispense the syringe 25. Thus, the dispensing operation of the FDG to the φ dispensing syringe 25 is performed. When the dispensing operation is repeated 'the liquid amount L of the FDG stored in the original liquid bottle 12 is lowered to a lower predetermined amount, When the minimum residual amount Lx is low, the FDG pair is performed by the storage bottle 22. The returning operation of the original liquid bottle 12 can be arbitrarily set. Here, the return operation of the FDG to the original liquid bottle 12 by the storage bottle 22 will be described with reference to Fig. 1A. First, in step S200, it is determined. Whether the liquid amount L of the FDG stored in the original liquid bottle 12 is smaller than the minimum residual amount Lx. When the result of the determination in step S200 is φ YES, the process proceeds to step S202, and the current FDG stored in the storage bottle 22 is calculated based on the following equation. The concentration of radioactivity Rtn.
Rtn = Rts x exp[-0.693 χ Δ T/Th] 在此，Rts爲等待於保管瓶22之FDG的當初之放射能 濃度，△ T爲由記憶放射能濃度Rts時的時刻Tts至現在時 刻Ttn爲止之經過時間，Th爲FDG之半衰期（1 〇9·8 )。 再者，若藉由放射線檢測器等，能直接測量被保管於保管 -23- (21) 1282273 瓶2 2之F D G的濃度的話，則可省略步驟S 2 Ο 2。 然後，在步驟S 2 0 4，根據所算出之現在的放射能濃 度Rtn，藉由下述方程式算出返回至原液瓶12之FDG的 返回液量Lr。 L r = R w X L w / R t η 在此，Rw爲原液瓶12內之目標原液濃度，Lw爲原液 瓶12內之目標原液量。例如，Rw爲3 00 ( MBq/ml ) ，Lw 爲 25 ( ml ) ° 其次，在步驟S206，判定在步驟S204所算出之返回 液量Lr是否較殘留於保管瓶22之FDG的等待液殘量Ly 小。再者，由於需要求取殘留於保管瓶22之FDG的等待 液殘量Ly，故保管瓶收容部24具有設置於原液瓶1 2之重 量測量器或攝影裝置等之液量檢測裝置爲佳。 然後，當在步驟S206之判定結果爲YES時，前進至 步驟S208，返回液量Lr之FDG被返回至原液瓶12。一方 面，當步驟 S 2 06之判定結果爲NO時，前進至步驟 S210，發出液量不足之警告。然後，在步驟S212，確認 是否將被保管於保管瓶22之全量的FDG返回。然後，當 步驟S212的確認結果爲YES時，前進至步驟S208，將等 待液殘量Ly之FDG返回至原液瓶12。一方面’當步驟 S2 12的確認結果爲NO時，不進行FDG之返回作業。 然後，能夠使用如此被返回至原液瓶12之FDG，持 -24- (22) 1282273 續進行對內部空間2之分注作業。 其次，說明本實施形態之作用及效果。 在本實施形態，也由於從原液瓶1 2將FDG的一部分 抽出後保管至保管瓶22，將殘留於原液瓶12之FDG稀 釋，故即使稀釋前的FDG爲高濃度，也能夠藉由稀釋來 增加爲了獲得相同的放射能量所需要之液量。因此，即使 在稀釋前，因極少量而產生不易進行利用吸引噴出氣之高 φ 精度的分注之虞的情況，亦可藉由爲了獲得相同放射能量 所必要之液量的增加，能夠謀求放射性液體之分注精度的 提昇。 特別是在本實施形態，藉由預先求取儲存於原液瓶1 2 內之FDG的濃度Re、與等待保管於保管瓶22之等待液量 Lt之關係，則不需要每次進行最小取出放射能量Rm的輸 入或各種計算，能夠進行更有效率之分注作業。 又，由於殘留於原容器之放射性液體之稀釋前的液量 φ L2係作成：根據最小取出放射能量Rm、容許最小噴出液 量Lm、及儲存於原液瓶12之FDG的液量L!所決定之容 許液量L。，故能夠在稀釋後將可進行利用注射器26之高 精度的分注之液量的FDG殘留於原容器內。 又，由於當原液瓶12內的FDG之放射能量形成預定 値以下時，可將被保管於保管瓶22的FDG之至少一部分 返回至原液瓶12，故進行分注所需要之FDG被補充，而 形成可持續進行分注作業。 再者，本發明不限於上述實施形態，可進行各種變 •25- (23) 1282273 更。例如，分注處所不限於分注注射器25，亦可爲瓶。 又，若能吸引放射性液體後加以噴出的話，亦可使用 注射器26以外者作爲吸引噴出器。其中，本發明係對於 在活塞具有裕度（背隙），進行極少量的放射性液體的分 注上有困難度之可棄式注射器的情況特別有效。 【圖式簡單說明】 φ 圖1係顯示放射性液體的分注裝置的結構之圖。 圖2係顯示放射性液體的分注方法之流程圖。 圖3係顯示原液瓶內的放射能量與液量之檢測流程之 流程圖。 圖4係顯示放射性液體的一部分被保管於保管瓶的狀 態之圖。 圖5係顯示將原液瓶內的放射性液體稀釋的狀態之 圖。 φ 圖6係顯示已被稀釋的放射性液體被分注到分注注射 器的狀態之圖。 圖7係顯示原液瓶內的放射性液體不足的狀態之圖。 圖8係顯示從保管瓶將放射性液體的一部分返回到原 液瓶的狀態之圖。 圖9係顯示放射性液體的分注方法之流程圖。 圖1 0係用來說明放射性液體的返回作業之流程圖。 【主要元件符號說明】 -26- (24) (24)1282273 1 〇 :分注裝置 1 2 :原液瓶 1 4 :放射線檢測器 1 6 :控制裝置 1 8 :重量測量器 20 :攝影裝置 22 :保管瓶 25 :分注注射器 26 :注射器 28 :稀釋液供給部 3 2 :注射器驅動裝置 34 :流路切換裝置Rtn = Rts x exp[-0.693 χ Δ T/Th] Here, Rts is the initial radiation energy concentration of the FDG waiting for the storage bottle 22, and ΔT is the time Tts from the memory radiation energy concentration Rts to the current time Ttn. The elapsed time, Th is the half-life of FDG (1 〇9·8). In addition, if the concentration of F D G stored in the storage -23-(21) 1282273 bottle 2 2 can be directly measured by a radiation detector or the like, the step S 2 Ο 2 can be omitted. Then, in step S 2 0 4, based on the calculated current radiation energy concentration Rtn, the return liquid amount Lr of the FDG returned to the original liquid bottle 12 is calculated by the following equation. L r = R w X L w / R t η Here, Rw is the target stock concentration in the original liquid bottle 12, and Lw is the target stock amount in the original liquid bottle 12. For example, Rw is 300 (MBq/ml) and Lw is 25 (ml). Next, in step S206, it is determined whether or not the amount of return liquid Lr calculated in step S204 is smaller than the waiting liquid residue of the FDG remaining in the storage bottle 22. Ly is small. In addition, since it is necessary to take the waiting liquid residual amount Ly of the FDG remaining in the storage bottle 22, it is preferable that the storage bottle accommodating portion 24 has a liquid amount detecting device such as a weight measuring device or a photographing device provided in the original liquid bottle 12. Then, when the result of the determination in step S206 is YES, the process proceeds to step S208, and the FDG of the returned liquid amount Lr is returned to the original liquid bottle 12. On the other hand, when the result of the determination in step S206 is NO, the process proceeds to step S210, and a warning that the liquid amount is insufficient is issued. Then, in step S212, it is confirmed whether or not the full amount of FDG stored in the storage bottle 22 is returned. Then, when the result of the confirmation in step S212 is YES, the process proceeds to step S208, and the FDG of the wait liquid amount Ly is returned to the original liquid bottle 12. On the one hand, when the confirmation result of the step S2 12 is NO, the return operation of the FDG is not performed. Then, the FDG thus returned to the original liquid bottle 12 can be used, and the dispensing operation for the internal space 2 is continued with -24-(22) 1282273. Next, the action and effect of the embodiment will be described. In the present embodiment, a part of the FDG is taken out from the original liquid bottle 12 and stored in the storage bottle 22, and the FDG remaining in the original liquid bottle 12 is diluted. Therefore, even if the FDG before dilution is high, it can be diluted. Increase the amount of liquid needed to achieve the same amount of radiant energy. Therefore, even before the dilution, it is difficult to perform the dispensing with high φ precision of the suction and discharge gas due to a small amount, and it is possible to achieve radioactivity by increasing the amount of liquid necessary for obtaining the same radiation energy. Increased accuracy of dispensing of liquids. In particular, in the present embodiment, by determining the relationship between the concentration Re of the FDG stored in the original liquid bottle 1 2 and the waiting liquid amount Lt waiting to be stored in the storage bottle 22, it is not necessary to perform the minimum extraction of the radiation energy each time. Rm input or various calculations enable more efficient dispensing operations. Further, the amount of liquid φ L2 before dilution of the radioactive liquid remaining in the original container is determined based on the minimum extracted radiation energy Rm, the allowable minimum discharge liquid amount Lm, and the liquid amount L! of the FDG stored in the original liquid bottle 12. The allowable liquid amount L. Therefore, it is possible to leave the FDG which can perform the high-precision dispensing of the syringe 26 in the original container after the dilution. Further, when the radiation energy of the FDG in the original liquid bottle 12 is formed to be less than or equal to a predetermined value, at least a part of the FDG stored in the storage bottle 22 can be returned to the original liquid bottle 12, so that the FDG required for dispensing is replenished. Form a sustainable dispensing operation. Furthermore, the present invention is not limited to the above embodiment, and various changes can be made to 25-(23) 1282273. For example, the dispensing position is not limited to the dispensing syringe 25, and may be a bottle. Further, if the radioactive liquid can be sucked and then ejected, a syringe 26 can be used as the suction ejector. Among them, the present invention is particularly effective in the case of a disposable syringe in which the piston has a margin (back gap) and it is difficult to dispense a very small amount of radioactive liquid. BRIEF DESCRIPTION OF THE DRAWINGS φ Fig. 1 is a view showing the structure of a dispensing device for a radioactive liquid. Fig. 2 is a flow chart showing a method of dispensing a radioactive liquid. Fig. 3 is a flow chart showing the flow of detecting the amount of radiation energy and the amount of liquid in the original liquid bottle. Fig. 4 is a view showing a state in which a part of the radioactive liquid is stored in the storage bottle. Fig. 5 is a view showing a state in which the radioactive liquid in the original liquid bottle is diluted. φ Fig. 6 is a view showing a state in which the diluted radioactive liquid is dispensed into the dispensing syringe. Fig. 7 is a view showing a state in which the radioactive liquid in the original liquid bottle is insufficient. Fig. 8 is a view showing a state in which a part of the radioactive liquid is returned from the storage bottle to the original liquid bottle. Figure 9 is a flow chart showing a method of dispensing a radioactive liquid. Figure 10 is a flow chart for explaining the return operation of the radioactive liquid. [Description of main component symbols] -26- (24) (24) 1282273 1 〇: Dispensing device 1 2 : Raw liquid bottle 1 4 : Radiation detector 1 6 : Control device 1 8 : Weight measuring device 20 : Photographic device 22 : Storage bottle 25: dispensing syringe 26: syringe 28: diluent supply unit 3 2 : syringe driving device 34: flow path switching device
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