• 대한핵의학회지
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• 제28권3호
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• pp.326-330
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• 1994

A $^{82}Sr/^{82}Rb$ generator was prepared by loading $^{82}Sr$ to preconditioned tin dioxide column. The generator was eluted by normal saline with flow rate up to 8m1/min, and the eluted radioactivity was monitored by dose calibrator. Radioactivity began to come out at 5ml and reached to peak around 9ml. The total eluted radioactivity increased linearly with flow rate, and the maximum obtained radioactivity was 35mCi at 8m1/min. The $^{82}Rb$ preparation was proven to be free from both strontium radioactivity and pyrogen. The $^{82}Rb$ was injected to normal female volunteer and positron emission tomographic Image of heart was obtained successfully.

• 대한방사성의약품학회지
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• 제5권2호
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• pp.71-78
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• 2019

Nuclear imaging is one of the most powerful measures for non-invasive diagnosis of myocardial vascular disease. Radionuclide such as ¹³N, ¹⁵O, ²⁰¹Tl and ⁸²Rb is used for the measurement of cardiac blood flow. ¹³N, ¹⁵O and ²⁰¹Tl are produced in cyclotrons while ⁸²Rb is obtained from generator. Rubidium (Rb), an alkali ion, behaves biologically like potassium, and accumulates in myocardial tissue. Rb has rapid blood clearance profile which allows the use of ⁸²Rb with a short physical half-life of 75 s for non-invasive evaluation of regional myocardial perfusion. There are several advantages of ⁸²Rb over other radioisotopes. An ultra-short half-life significantly reduces the exposure of patients to radiation and allows to repeat injections for studying the effects of medical intervention. As a positron emitter, ⁸²Rb allows positron emission tomography (PET) imaging which have shown superior diagnostic performances. ⁸²Rb can be produced from generator by decay of its parent ⁸²Sr. However, the preparation of ⁸²Sr is difficult, because appropriate purity is required to meet the specification of the product. Recently reported procedure from ARRONAX research institute showed that a Chelex-100 resin is sufficient for this purpose and additional column is not necessary. Whereas Brookhaven National Laboratory (BNL) procedure contains three ion exchange resin separation, including Chelex-100 resin. Currently, since ⁸²Sr production site is non-existent in Korea, Korea Atomic Energy Research Institute (KAERI) has plan to produce ⁸²Sr within specifications. We compared ⁸²Sr purification procedures reported from ARRONAX and BNL to investigate the most suitable procedure for our conditions.

• 대한방사성의약품학회지
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• 제7권2호
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• pp.119-125
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• 2021

⁸²Sr for ⁸²Rb generator was produced through the irradiation of the proton beam on the ^nat.RbCI target at the target irradiation facility installed at the end of the Rl-dedicated beamline of the 100 MeV proton linear accelerator of KOMAC (Korea Multi-purpose Accelerator Complex). The average current of the proton beam was 1.2 µA for irradiation time of 150 min. For the separation and purification of the ⁸²Sr from ^nat.RbCI irradiated, Chelex-100 resin was used. The activities of ⁸²Sr in the irradiated ^nat.RbCI target solution and after purification were 45.29 µCi and 43.4 µCi, respectively. The separation and purification yield was 95.8%. As an adsorbent to be filled in the generator for ⁸²Sr adsorption hydrous tin oxide was selected. The adsorption yield of ⁸²Sr into the generator adsorbent was > 99 %, and the total amount of ⁸²Sr adsorbed to the generator was 21.6 µCi as of the day of the ⁸²Rb elution experiment. When the elution amount was 22 mL, the maximum⁸²Rb elution yield was 93.3%, and the elution yield increased as the flow rate increased. After the eluted ⁸²Rb was filled in the correction phantom of the small PET for animals, a PET image was taken. The image scan time was set to 5 min, and the phantom PET image was successfully obtained. As results of impurity analysis on eluted ⁸²Rb using ICP-MS, ^nat.Rb stable isotopes that compete in vivo of ⁸²Rb were identified as undetected levels and were determined to be No-Carrier-Added (NCA).

• Journal of Radiation Protection and Research
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• 제20권4호
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• pp.265-274
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• 1995

Co-60은 원자력발전소에서 발생하는 부식생성물로서 중저준위 방사성폐기물에 함유된 가장 중요한 핵종중 하나다 방사성폐기물처분장 충전물로 많이 사용되는 점토층을 통한 Co-60 확산실험을 하여 밀도변화에 따른 확산계수를 구하였다. Co-60의 확산실험 기간은 점토 밀도에 따라 최소 9시간에서 최대 120일이 걸렸으며, 확산계수는 저밀도인 $0.41g/cm^3$에서 $8.79{\times}10^{11}m^2/s$로부터 고밀도인 $2.03g/cm^3$에서 $6.82{\times}10^{14}m^2/s$까지 급격히 감소하는 현상을 보여주었다. 그리고, 기존에 수행한 연구와 비친 결과 다음과 같은 사실을 확인할 수 있었다. 첫째, 2가 이온인 Sr나 Co이온은 저밀도 점토층에서 1가 이온인 Cs 보다 큰 확산속도를 갖는다. 이러한 현상은 점토표면에 흡착되는 양이온들의 수화상태로 부터 설명할 수 있었다. 둘째, Co 이온의 경우 저밀도에서는 Sr이온보다도 큰 확산계수를 보여준다. 이러한 현상은 Co이온의 수화반경이 Sr이온보다 크다는 사실로 해석할 수 있었다. 셋째, 밀도가 증가함에 따라 Co 이온의 확산계수는 Cs 이온보다도 작은 값으로 급격히 감소한다. 이러한 현상은 점토층의 밀도가 증가함에 따라 점토표면과 화학결합을 하는 Co 이온들이 급격히 증가하고, 점토의 결정속으로 잠적하여 점토의 일부가 되는 이온들이 급격히 증가하기 때문인 것으로 생각된다. 이와 같은 현상들은 표면확산이론으로 설명이 가능하며 특히 저밀도 점토층에서 Co-60의 확산속도가 크다는 것은 중 저준위 방사성 폐기물 처분장 설계나 안전성 평가에 매우 중요한 자료가 될 것이다.