TWI543939B - Automatic extraction analysis method of trans-uranium element - Google Patents
Automatic extraction analysis method of trans-uranium element Download PDFInfo
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本發明有關一種超鈾元素之自動萃取分析方法,其係使用自動化固相萃取系統針對含超鈾元素之液態檢測物進行自動化分離純化後,以阿伐能譜儀進行計測超鈾元素。 The invention relates to an automatic extraction and analysis method for transuranic elements, which uses an automated solid phase extraction system to automatically separate and purify liquid detection materials containing transuranic elements, and then measures the transuranic elements by using an Alpha spectrometer.
放射性核種是核子反應的重要產物之一,為確保核能設施之安全運轉及保護環境不受輻射污染,需要了解與評估放射性產物之濃度、分佈與影響,故自核能技術開始發展應用至今,相關放射性核種之分析與鑑定一直是核能工業的必備技術。 Radioactive nucleus is one of the important products of nuclear reaction. In order to ensure the safe operation of nuclear energy facilities and protect the environment from radiation pollution, it is necessary to understand and evaluate the concentration, distribution and influence of radioactive products. Therefore, since the development and application of nuclear energy technology, related radioactivity The analysis and identification of nuclear species has always been an essential technology for the nuclear energy industry.
放射性核種中之超鈾元素(Trans-Uranium Element)的製造,基本上可分為兩種方法:(1)重原子核捕獲中子後經β-衰變增加原子序(例如鈾元素經過中子照射後就會產生超鈾元素,中子撞擊鈾-238產生鈽-239,鈾-238就是鈽-239的母原子核);(2)以荷電加速器加速荷電粒子撞擊母原子核(例如母原子核鋦-244經由迴旋加速器加速碳-13衝擊而製成鍩-251)。在核燃料循環設施中會產生超鈾放射性廢物,稱為超鈾廢棄物,該超鈾廢棄物大致上包含水泥、有機物等各種物質,超鈾元素的半衰期長達數十萬年,易溶於水且不容易被吸附,在環境中的遷移性很高,對環境會產生廣泛而長久的影響,且超鈾元素多半釋放阿伐(α)粒子輻射,阿伐粒子具有生理劇毒性,若攝入體內將會造成不可逆的傷害,根據我國(中華民國)低放射性廢棄物最終處置及其設施安全管理規則,低放射 性廢棄物依其放射性核種濃度分類可分為A類、B類、C類與超C類,目前已將TRU核種(半衰期大於5年之超鈾阿伐放射核種)列為放射廢料管制的主要核種之一,其單一長半衰期核種濃度值以為3.7kBq/g作為分類標準與放射性廢棄物之包裝根據,國內核能電廠、放射性廢棄物貯存場與環境均需要長期監控,因此持續改善TRU分析方法,使其達到更好的分析結果有其必要性。 The manufacture of Trans-Uranium Element in radioactive nucleus can be basically divided into two methods: (1) After the neutron captures the neutron, the atomic sequence is increased by β - decay (for example, after the uranium element is irradiated by neutrons) It will produce transuranic elements, neutrons impact uranium-238 to produce 钸-239, uranium-238 is the parent nucleus of 钸-239); (2) accelerate the charged particles to strike the parent nucleus with a charge accelerator (eg mother nucleus 244-244 via The cyclotron accelerates the carbon-13 impact to make 鍩-251). In the nuclear fuel cycle facilities, transuranic radioactive waste, called transuranic waste, is generally produced. The transuranic waste contains roughly various substances such as cement and organic matter. The transuranic element has a half-life of hundreds of thousands of years and is easily soluble in water. It is not easy to be adsorbed, has high mobility in the environment, and has a wide and long-lasting impact on the environment, and most of the transuranic elements release the radiation of the Alpha (α) particles, which are physiologically toxic, if ingested. The body will cause irreversible damage. According to China (Republic of China) low-level radioactive waste final disposal and its facility safety management rules, low-level radioactive waste can be classified into Class A, Class B, Class C and Super according to its radioactive nuclear species concentration. In category C, TRU nucleus (transuranic arsenic nucleus with a half-life of more than 5 years) has been listed as one of the main nuclear species for radiation waste control, and its single long half-life nucleus concentration value is 3.7kBq/g as a classification standard and radioactive waste. According to the packaging of the goods, domestic nuclear power plants, radioactive waste storage sites and the environment require long-term monitoring, so the TRU analysis method is continuously improved to achieve better scores. The results of its necessity.
我國於過去數十年來,習用上均是利用放射分析化學方法(radioanalytical methods,RA法)配合阿伐能譜儀(alpha ray spectrometer)等,對超鈾廢棄物進行超鈾元素分析。 In the past few decades, China has used radioanalytical methods (RA method) and alpha ray spectrometer to analyze the transuranium waste.
超鈾廢棄物在進行放射分析化學方法之前,通常需要進行前處理,該前處理包括:熔解、離子交換與共沉澱(coprecipitation),該等前處理的共同缺點為耗時,通常需要花費數天至數週才能用於進行放射分析化學方法,除了影響分析時效性外,於進行高活度樣本分析時,前處理步驟中,操作人員會接受到相當程度之輻射曝露劑量,造成操作上安全問題。此外、因為超鈾元素易溶於水中,尤其是Pu易殘留於容器壁,而且以往的超鈾元素分析方法中之前處理通常需要進行數次加熱、稀釋及容器轉移,故會造成超鈾元素於操作過程中流失,導致分析結果偏低,甚至需要再進行濃縮才可被儀器(例如阿伐能譜儀)偵測到。 Ultra-uranium waste usually requires pre-treatment before performing radiochemical analysis. The pre-treatment includes: melting, ion exchange and coprecipitation. The common disadvantage of these pretreatments is time-consuming and usually takes several days. It can take several weeks to be used for radiochemical analysis. In addition to affecting the timeliness of analysis, in the high-activity sample analysis, the operator will receive a considerable amount of radiation exposure during the pre-treatment step, resulting in operational safety issues. . In addition, because the transuranic element is easily soluble in water, especially Pu is easy to remain in the container wall, and the previous treatment of the transuranium element analysis usually requires several heating, dilution and container transfer, which will cause the transuranic element to Loss during operation, resulting in low analytical results, even need to be concentrated before being detected by instruments (such as the Alvar spectrometer).
早期的管柱流洗操作主要係由操作者進行手動操作,因為管柱體積有限,再者由於僅靠重力讓管柱液體慢慢流出,人員必須站在萃取管柱旁邊慢慢加,每一個步驟都要等前一流洗液流洗完才能再加入下一步驟的流洗液,因此操作人員等待的時間很長,相對所接受的暴露劑量增加 The early column flow washing operation was mainly performed manually by the operator. Because the column volume was limited, and the pipe column liquid was slowly flowed out by gravity alone, the personnel had to stand slowly beside the extraction column, each one The steps must be waited for before the first-stage washing liquid is washed before the next step of the washing liquid is added, so the operator waits for a long time, and the relative exposure dose is increased.
鑑於上述問題點,本發明人等針對如何以較短時間、以較少試劑量即可進行分析因而可抑制成本之方法進行研究,發現藉由利用自動化固相萃取(Automatic Soild phase extraction,ASPE)系統進行自動化分 離純化後,再利用阿伐能譜儀進行測量,而可達成上述目的,並且藉由以電腦程式進行控制,而可減少操作誤差並可降低分析人員操作時所受之輻射暴露劑量,因而完成本發明。 In view of the above problems, the inventors of the present invention have conducted research on how to perform analysis in a shorter time and with a smaller amount of reagents, thereby suppressing cost, and found that by using Automatic Soild phase extraction (ASPE). System automation After purification, the measurement can be carried out by using the Ava spectrometer, and the above object can be achieved, and by controlling by computer program, the operation error can be reduced and the radiation exposure dose of the analyst can be reduced, thereby completing this invention.
本發明係有關一種超鈾元素之自動萃取分析方法,其係使用自動化固相萃取系統針對液態檢測物進行自動化分離純化後,以阿伐能譜儀進行計測超鈾元素。 The invention relates to an automatic extraction analysis method for transuranic elements, which uses an automated solid phase extraction system to automatically separate and purify liquid detection materials, and then measures the transuranic elements by using an Alpha spectrometer.
本發明所稱之超鈾元素意指原子序超過U-92之放射性元素,舉例為例如Am、Cm、Pu等。 The term "transuranic material" as used in the present invention means a radioactive element having an atomic order exceeding U-92, and is exemplified by, for example, Am, Cm, Pu, and the like.
本發明之超鈾元素之自動萃取分析方法包括下列步驟:(1)將液態待測樣品移至燒杯中蒸乾,並於其中添加1M~3M(較好為2M)硝酸及0.1M~0.5M(較好為0.3M)抗壞血酸(ascorbic acid)使其成為一定體積,獲得一混合物。此步驟係將樣品中存在之各種價數的Pu,以抗壞血酸將各種價數Pu均還原成Pu+3,如此將有助於TRU樹脂吸附Pu並排出其他干擾物;(2)將約5~15dpm/g(較好為10dpm/g)之Am-243及Pu-242示蹤劑(tracing agent)添加於步驟(1)所得之混合物中,並將該混合物注入自動化固相萃取系統之TRU樹脂管柱中,此步驟中之示蹤劑係選擇欲分析元素的同位素,該同位素物性與化性與欲分析元素相似,因此藉由測定所回收之示蹤劑回收率,可回推待測樣品中的超鈾元素確實含量;(3)使用下述溶洗液依序進行階段性溶洗:(3a)含0.1M~0.5M抗壞血酸之1M~3M HNO3溶液,流洗TRU樹脂;(3b)含0.05M~0.3M(較好0.1M NaNO2)之1M~3M(較好2M)HNO3溶液,以將Pu+3轉變為Pu+4,以避免在下個步驟使用HCl流洗Am時之Pu會同時被洗出,可使Pu仍吸附在TRU樹脂中;(3c)3M~5M(較好4M)之HCl,溶洗出示蹤劑Am- 243,於此步驟中當待測樣品中含有Cm元素時,Cm會隨著Am一起被流洗出,則亦可同時分析Cm;(3d)以0.05M~0.2M(較好0.1M)之NH4HC2O4水溶液溶洗出Pu;(4)接著使步驟(3c)所得之含Am及/或Cm之溶洗液及步驟(3d)所得之含Pu之溶洗液各添加於含有一試片(可為不鏽鋼316或304之圓形試片)的電鍍裝置(型號為:GPS-3030DD,INSTEK,China)以0.5A~1.0A(較好為0.8A)分別進行電鍍1~3小時(2小時為佳),獲得電鍍片;詳細之電鍍條件如下:(4a)使於上述步驟(3c)及(3d)分別所得之含Am及/或(Cm)之溶洗液以及含Pu之溶洗液蒸乾後,於其中添加0.5~2M(較好1M)H2SO4並蒸乾液體回溶後,加入指示劑百里酚藍(thymol blue)數滴,分別獲得電沉積液。(4b)以濃NH4OH將上述電沉積液調整溶液pH為2~3,此時溶液呈橙色。(4c)將不銹鋼片先以酒精洗淨並裝入電沉積槽內,以白金線作為陽極及以電沉積片作為陰極,並調整期間之間距後予以固定組裝。(4d)將步驟(4c)所得之電沉積液倒入電沉積槽,以0.8A電沉積120分鐘,於電沉積結束前加入數滴(3滴為佳)30% NH4OH以調整電沉積液之酸鹼值,有助於待測核種附著於電鍍片上,並等待1分鐘後移除白金陽極;及(5)將步驟(4)所得之電鍍片以阿伐能譜儀進行測定,計測完成後,開啟圖譜依能量圈選能峰(添加之示蹤劑Am-243能量為5.27MeV、Am-241能量為5.48MeV,Pu-238能量5.49MeV、Pu-239+Pu-240能量5.15/5.168MeV,而添加之示蹤劑Pu-242能量為4.9MeV),分別記錄各核種及示蹤劑之計數值及計測腔效率,計算回收率及各核種活度,求出樣品中超鈾元素活度。 The automatic extraction analysis method of the transuranic element of the invention comprises the following steps: (1) moving the liquid sample to be tested and evaporating to a beaker, and adding 1M~3M (preferably 2M) nitric acid and 0.1M~0.5M thereto. (preferably 0.3 M) ascorbic acid is made into a volume to obtain a mixture. This step is to reduce the various valences of Pu to asPu +3 with various valences of Pu present in the sample, which will help the TRU resin to adsorb Pu and discharge other interferents; (2) about 5~ 15dpm/g (preferably 10dpm/g) Am-243 and Pu-242 tracer agent are added to the mixture obtained in the step (1), and the mixture is injected into the TRU resin of the automated solid phase extraction system. In the column, the tracer in this step selects the isotope of the element to be analyzed. The isotope is similar in chemical properties to the element to be analyzed, so the sample to be tested can be pushed back by measuring the recovered tracer recovery rate. The content of the transuranic element in the medium; (3) sequential washing with the following solvent: (3a) 1M ~ 3M HNO 3 solution containing 0.1M ~ 0.5M ascorbic acid, flow washing TRU resin; (3b 1M~3M (preferably 2M) HNO 3 solution containing 0.05M~0.3M (preferably 0.1M NaNO 2 ) to convert Pu +3 to Pu +4 to avoid the use of HCl flow in the next step The Pu will be washed out at the same time, so that Pu can still be adsorbed in the TRU resin; (3c) 3M~5M (better 4M) HCl, and the tracer Am-243 is eluted, in the sample to be tested in this step. When Cm is contained, Cm will be washed out with Am, and Cm can be analyzed at the same time; (3d) Pu is eluted with 0.05M~0.2M (preferably 0.1M) NH 4 HC 2 O 4 aqueous solution. (4) then adding the Am and/or Cm-containing solution obtained in the step (3c) and the Pu-containing solution obtained in the step (3d) to each of the test pieces (which may be stainless steel 316 or 304) The plating device of the round test piece (model: GPS-3030DD, INSTEK, China) is plated for 0.5 to 1.0 hour (preferably 0.8A) for 1 to 3 hours (2 hours is preferred) to obtain the plated piece. The detailed plating conditions are as follows: (4a) the Am and/or (Cm)-containing solvent solution obtained in the above steps (3c) and (3d) and the Pu-containing solution are evaporated to dryness, and then added thereto. After 0.5~2M (preferably 1M) H 2 SO 4 and evaporated to dryness, a few drops of the indicator thymol blue were added to obtain an electrodeposition solution. (4b) The above electrodeposition solution was adjusted to have a pH of 2 to 3 with concentrated NH 4 OH, at which time the solution was orange. (4c) The stainless steel sheet was first washed with alcohol and charged into an electrodeposition tank, with a platinum wire as an anode and an electrodeposited sheet as a cathode, and fixedly assembled after adjusting the distance therebetween. (4d) Pour the electrodeposition solution obtained in the step (4c) into the electrodeposition bath, electrodeposite at 0.8 A for 120 minutes, and add a few drops (3 drops of preferably) 30% NH 4 OH to adjust the electrodeposition before the end of electrodeposition. The pH value of the liquid helps the test nucleus to adhere to the electroplated sheet, and waits for 1 minute to remove the platinum anode; and (5) the electroplated sheet obtained in the step (4) is measured by an argon spectrometer, and the measurement is performed. After completion, open the spectrum according to the energy circle selection peak (additional tracer Am-243 energy is 5.27MeV, Am-241 energy is 5.48MeV, Pu-238 energy is 5.49MeV, Pu-239+Pu-240 energy is 5.15/ 5.168MeV, and the added tracer Pu-242 energy is 4.9MeV), record the count value of each nuclear species and tracer and the efficiency of the measurement chamber, calculate the recovery rate and the activity of each nucleus, and find the transuranic activity in the sample. degree.
本發明之自動萃取分析方法中,當待測樣品為固態時,則在步驟(1)之前,進一步進行下列步驟:於固態待測樣品中加入濃硝酸及 鹽酸並放入微波消化裝置(Microwave Digestion System,MARS 5,CEM,USA)中進行消化,獲得液態待測樣品,供於進行前述步驟(1)。 In the automatic extraction analysis method of the present invention, when the sample to be tested is in a solid state, before the step (1), the following steps are further carried out: adding concentrated nitric acid to the solid sample to be tested and Hydrochloric acid was placed in a microwave digestion apparatus (Microwave Digestion System, MARS 5, CEM, USA) for digestion to obtain a liquid sample to be tested for the aforementioned step (1).
本發明之自動萃取分析方法,其中於步驟(2)中將樣品注入自動化固相萃取系統之TRU樹脂管柱之前,進行下述溶洗:將含0.1M~0.5M(較好為0.3M)抗壞血酸之1M~3M(較好為2M)HNO3溶液,流洗TRU樹脂,以將TRU樹脂中可能之干擾物排出。 The automatic extraction analysis method of the present invention, wherein before the sample is injected into the TRU resin column of the automated solid phase extraction system in the step (2), the following dissolution is performed: 0.1M to 0.5M (preferably 0.3M) ascorbic acid 1M ~ 3M (preferably 2M) HNO 3 solution, the elution TRU resin, the resin may TRU to interfere with the exhaust.
本發明之自動萃取分析方法中,待測樣品可為超鈾廢棄物,如超鈾乾廢料、廢樹脂、沉渣廢料、濾紙或經污染之土壞等。 In the automatic extraction analysis method of the present invention, the sample to be tested may be a trans-uranium waste such as a dry uranium waste, a waste resin, a sediment waste, a filter paper or a damaged soil.
圖1顯示本發明之自動萃取分析方法之實施例流程圖。 BRIEF DESCRIPTION OF THE DRAWINGS Figure 1 is a flow chart showing an embodiment of the automatic extraction analysis method of the present invention.
本發明將以下述實施例進一步加以說明,惟該等實施例僅用以說明目的而不用以限制本發明之範圍,本發明之範圍應由申請專利範圍之內容加以限制。 The invention is further illustrated by the following examples, which are intended to be illustrative only and not to limit the scope of the invention, and the scope of the invention is limited by the scope of the claims.
本發明之超鈾元素之自動萃取分析方法係以下述步驟進行。本實施例中,以待測樣品為固態樣品為例加以說明。 The automatic extraction analysis method of the transuranic element of the present invention is carried out in the following procedure. In this embodiment, the sample to be tested is taken as a solid sample as an example.
1. 準備液態待測物:將水泥:71.54%,NaCl:12.61%,Ba(OH)2:6.00%,Na2SO4:4.50%,NaOH:3.15%,NaNO3:1.18%,Na2CO3:0.62%,Na3PO4:0.26%,NaHCO3:0.14%以水充分混合,製作水泥塊,作為固體樣本。接著秤取該固體樣本0.25克放入消化瓶中,並添加濃硝酸9ml及鹽酸4ml,為了防止酸性溶液作用產氣,因此在消化瓶未加蓋情況下靜置一分鐘,再蓋上消化瓶靜置二十分鐘預先硝化後放入微波消化裝置,本實驗中以一次消化兩瓶樣品為例,說明消化裝置參數:該消化裝置之最高功率為300W,操作功率為最高功率的56%,以升溫時間5.5分鐘,自室溫升溫至溫度180℃,並在該溫度維持11.5分鐘,獲得消化液後, 再將消化液移至燒杯蒸至約乾。 1. Prepare the liquid test substance: cement: 71.54%, NaCl: 12.61%, Ba(OH) 2 : 6.00%, Na 2 SO 4 : 4.50%, NaOH: 3.15%, NaNO 3 : 1.18%, Na 2 CO 3 : 0.62%, Na 3 PO 4 : 0.26%, NaHCO 3 : 0.14% was sufficiently mixed with water to prepare a cement block as a solid sample. Then, 0.25 g of the solid sample was weighed and placed in a digestion bottle, and 9 ml of concentrated nitric acid and 4 ml of hydrochloric acid were added. In order to prevent the gas from being produced by the acidic solution, the digested bottle was allowed to stand for one minute without being covered, and then the digestive bottle was covered. After standing for 20 minutes, it was pre-nitrated and placed in a microwave digestion unit. In this experiment, two samples of one sample were digested at one time to illustrate the parameters of the digestion unit: the highest power of the digestion unit was 300 W, and the operating power was 56% of the highest power. The temperature was raised for 5.5 minutes, the temperature was raised from room temperature to a temperature of 180 ° C, and maintained at this temperature for 11.5 minutes. After obtaining the digestive juice, the digested juice was transferred to a beaker and steamed to about dryness.
2. 於乾燥物中加入含0.3M抗壞血酸之2M硝酸直至容量為15mL,將待測樣品中各種價數之Pu還原成Pu+3,獲得混合物。若所得混合物中有明顯可見雜質或懸浮液,則須使用濾紙例如使用Whatman No.42進行過濾後,於其中添加分別為10dpm/g左右之Am-243及Pu-242作為示蹤劑。 2. The dried solution containing ascorbic acid was 0.3M to 2M nitric acid until the capacity of 15mL, reducing the number of samples to be tested in a variety of monovalent Pu to Pu +3, to obtain a mixture. If there are clearly visible impurities or suspensions in the resulting mixture, it is necessary to use a filter paper, for example, filtration using Whatman No. 42, and then add Am-243 and Pu-242, respectively, at about 10 dpm/g as a tracer.
3. 使用Eichrom Technology公司生產之TRU樹脂(粒徑100~150μm)2ml放入自動化固相萃取系統(Automatic Solid Phase Extraction system,SPE,Biotage RapidTrace+,Sweden)中之填充管柱中,先使用20mL之含0.3M L-抗壞血酸之2M硝酸以3ml/min之流速對管柱進行流洗,以將TRU樹脂中可能之干擾物排出。 3. Using 2ml of TRU resin (particle size 100~150μm) produced by Eichrom Technology, put it into the filling column in the Automatic Solid Phase Extraction system (SPE, Biotage RapidTrace + , Sweden), first use 20mL The 2M nitric acid containing 0.3 M L-ascorbic acid was subjected to a flow wash at a flow rate of 3 ml/min to discharge possible interferences in the TRU resin.
4. 使用下述溶洗液依序進行階段性溶洗:(a)使20mL之含0.3M L-抗壞血酸之2M硝酸以3ml/min之流速對管柱進行流洗;(b)使5mL之含0.1M NaNO2之2M HNO3溶液以3ml/min之流速對管柱進行流洗,而將Pu+3轉變為Pu+4;(c)使20mL之4M HCl以3ml/min之流速溶洗出示蹤劑Am-243;及(d)使0.1M NH4HC2O4水溶液以10ml/min之流速對管柱進行流洗而溶洗出Pu; 4. Periodically elute sequentially using the following solvent: (a) 20 mL of 2 M nitric acid containing 0.3 M L-ascorbic acid was flow-washed at a flow rate of 3 ml/min; (b) 5 mL The 2M HNO 3 solution containing 0.1 M NaNO 2 was subjected to flow washing at a flow rate of 3 ml/min, and Pu +3 was converted to Pu +4 ; (c) 20 mL of 4 M HCl was dissolved at a flow rate of 3 ml/min. Tracer Am-243; and (d) 0.1M NH 4 HC 2 O 4 aqueous solution at a flow rate of 10 ml / min to wash the column to dissolve Pu;
5. 接著使步驟4.所得之含Pu之溶洗液於一不鏽鋼316圓形試片上,利用電鍍裝置(型號為:GPS-3030DD,INSTEK,China)以0.8A進行電鍍2小時,獲得電鍍片;詳細之電鍍條件如下:於上述步驟4.(c)所得之含Am之溶洗液及步驟(d)所得之含Pu之溶洗液中分別加入1M H2SO4並使蒸發近乾液體回溶後,加入指示劑百里酚藍(thymol blue)數滴,分別獲得電沉積液。(4b)以濃NH4OH將各電沉積液調整溶液pH為2~3,此時溶液呈橙色。(4c)將不銹鋼片先以酒精洗淨並裝入電沉積槽內,以白金 線作為陽極及以電沉積片作為陰極,並調整期間之間距後予以固定組裝。(4d)將步驟(4c)所得之各電沉積液倒入各電沉積槽,以0.8A電沉積2小時,於電沉積結束前加入3滴30% NH4OH,並等待1分鐘後移除白金陽極。 5. Next, the Pu-containing solution obtained in the step 4. was subjected to electroplating on a stainless steel 316 round test piece by electroplating for 2 hours using a plating apparatus (Model: GPS-3030DD, INSTEK, China) to obtain an electroplated sheet. The detailed plating conditions are as follows: 1M H 2 SO 4 and evaporation of the near dry liquid are respectively added to the Am-containing solution obtained in the above step (c) and the Pu-containing solution obtained in the step (d). After re-dissolving, a few drops of the indicator thymol blue were added to obtain an electrodeposition solution. (4b) Adjust the pH of each electrodeposition solution to 2 to 3 with concentrated NH 4 OH, at which time the solution is orange. (4c) The stainless steel sheet was first washed with alcohol and charged into an electrodeposition tank, with a platinum wire as an anode and an electrodeposited sheet as a cathode, and fixedly assembled after adjusting the distance therebetween. (4d) Pour each electrodeposition liquid obtained in the step (4c) into each electrodeposition bath, electrodeposite at 0.8 A for 2 hours, add 3 drops of 30% NH 4 OH before the end of electrodeposition, and wait for 1 minute to remove Platinum anode.
6. 將步驟5.所得之電鍍片以多通道阿伐能譜儀進行測定,計測完成後,開啟圖譜依能量圈選能峰(添加之示蹤劑Am-243能量為5.27MeV、Am-241能量為5.48MeV,Pu-238能量5.49MeV、Pu-239+Pu-240能量5.15/5.168MeV,而添加之示蹤劑Pu-242能量為4.9MeV),分別記錄各核種及示蹤劑之計數值及計測腔效率,計算回收率及各核種活度,求出樣品中超鈾元素活度。結果,Am-243之回收率為67±10%,Pu-242回收率為42±10%。 6. The plated piece obtained in step 5. is measured by a multi-channel Ava spectrometer. After the measurement is completed, the spectrum is selected according to the energy circle (the energy of the tracer Am-243 added is 5.27 MeV, Am-241). The energy is 5.48 MeV, the energy of Pu-238 is 5.49 MeV, the energy of Pu-239+Pu-240 is 5.15/5.168 MeV, and the energy of the added tracer Pu-242 is 4.9 MeV), and the counts of each nuclear species and tracer are recorded separately. The numerical value and the efficiency of the measurement chamber were calculated, and the recovery rate and the activity of each nucleus were calculated to determine the activity of the transuranic element in the sample. As a result, the recovery of Am-243 was 67 ± 10%, and the recovery of Pu-242 was 42 ± 10%.
本實施例中除了實施例1中之步驟1之液體待測樣本製備係將純水1ml加入10mL的0.3M抗壞血酸之2M硝酸中,再加入1mL Am-243以及1mL Pu-242(活度約為10dpm左右液體混合物作為待測樣本進行實驗測試以外,餘與實施例1同樣操作,獲得之結果為Am-243回收率係85±5%,Pu-242係65±5%。 In this example, except for the liquid sample to be tested in the first step of the embodiment 1, 1 ml of pure water was added to 10 mL of 2 M nitric acid of 0.3 M ascorbic acid, and then 1 mL of Am-243 and 1 mL of Pu-242 were added (the activity was about The liquid mixture was subjected to an experimental test as a sample to be tested at about 10 dpm, and the same operation as in Example 1 was carried out to obtain an Am-243 recovery rate of 85 ± 5% and a Pu-242 system of 65 ± 5%.
本發明之上述步驟3及4均在自動化固相萃取系統中進行,各溶洗參數例如溶洗流速等可利用電腦加以控制,故而可減少操作人員接受放射線之劑量。 The above steps 3 and 4 of the present invention are all carried out in an automated solid phase extraction system, and each elution parameter such as the elution flow rate can be controlled by a computer, thereby reducing the dose of radiation received by the operator.
本發明之超鈾元素之自動萃取分析方法係利用自動化固相萃取系統進行自動化分離純化後,以阿伐能譜儀進行計測,而為分析超鈾元素的全自動萃取純化分析方法。本發明可大幅縮短操作時間、減少試劑使用、有效抑低成本,且透過電腦程式自動控制萃取純化運作,可減少人員操作誤差,並可降低分析人員作業時所受的輻射曝露劑量。本發明之自動化固相萃取系統為封閉式系統,超鈾元素不易於分析過程中逸失,相較於以往方法,能保存原有之超鈾 元素,可確保分析結果之正確性。綜合以上優點,本發明十分適合應用於核能電廠、核廢料貯存場及環境監控利用。 The automatic extraction analysis method of the transuranic element of the invention is automated separation and purification by an automated solid phase extraction system, and then measured by an Ava spectrometer, and is a fully automatic extraction and purification analysis method for analyzing the transuranic element. The invention can greatly shorten the operation time, reduce the use of reagents, and effectively reduce the cost, and automatically controls the extraction and purification operation through the computer program, can reduce the operation error of the personnel, and can reduce the radiation exposure dose received by the analyst. The automated solid phase extraction system of the invention is a closed system, and the transuranic element is not easy to escape during the analysis, and the original transuranium can be preserved compared with the conventional method. Elements to ensure the correctness of the analysis results. Based on the above advantages, the present invention is well suited for use in nuclear power plants, nuclear waste storage sites, and environmental monitoring and utilization.
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