核技术
覈技術
핵기술
Nuclear Techniques
2015年
9期
090301-1-090301-6
,共1页
牟婉君%李兴亮%余钱红%蹇源%魏洪源%杨玉山
牟婉君%李興亮%餘錢紅%蹇源%魏洪源%楊玉山
모완군%리흥량%여전홍%건원%위홍원%양옥산
钙钛矿%固化体%抗浸出性能%辐照
鈣鈦礦%固化體%抗浸齣性能%輻照
개태광%고화체%항침출성능%복조
Perovskite-type%Waster forms%Leaching behavior%Radiation
为研究90Sr 衰变子体对90SrTiO3固化体结构稳定性的影响,以 C4H6O4Sr·0.5H2O、TiO2及 ZrOCl2·8H2O粉体作为原料,按照化学计量比 SrZrxTi1?xO3(0≤x<1)设计配方,采用高温固相法制备一系列固化体。利用 X射线衍射光谱(X-ray Diffraction, XRD)、扫描电镜(Scanning Electron Microscope, SEM)及红外(Fourier Transform Infrared, FT-IR)谱仪对制备固化体的物相、结构和微观形貌进行分析表征,并对其抗浸出性能和辐照性能进行了研究。结果表明,当 x<0.5时,固化体为单一物相;当 x≥0.5时,固化体中出现第二相。固化体中的 Sr2+、Zr4+的浸出浓度随浸泡时间而增大,在浸泡42 d 时,Sr2+的最大浸出浓度为0.0065μg.mL?1,Zr4+的最大浸出浓度为0.01μg.mL?1。
為研究90Sr 衰變子體對90SrTiO3固化體結構穩定性的影響,以 C4H6O4Sr·0.5H2O、TiO2及 ZrOCl2·8H2O粉體作為原料,按照化學計量比 SrZrxTi1?xO3(0≤x<1)設計配方,採用高溫固相法製備一繫列固化體。利用 X射線衍射光譜(X-ray Diffraction, XRD)、掃描電鏡(Scanning Electron Microscope, SEM)及紅外(Fourier Transform Infrared, FT-IR)譜儀對製備固化體的物相、結構和微觀形貌進行分析錶徵,併對其抗浸齣性能和輻照性能進行瞭研究。結果錶明,噹 x<0.5時,固化體為單一物相;噹 x≥0.5時,固化體中齣現第二相。固化體中的 Sr2+、Zr4+的浸齣濃度隨浸泡時間而增大,在浸泡42 d 時,Sr2+的最大浸齣濃度為0.0065μg.mL?1,Zr4+的最大浸齣濃度為0.01μg.mL?1。
위연구90Sr 쇠변자체대90SrTiO3고화체결구은정성적영향,이 C4H6O4Sr·0.5H2O、TiO2급 ZrOCl2·8H2O분체작위원료,안조화학계량비 SrZrxTi1?xO3(0≤x<1)설계배방,채용고온고상법제비일계렬고화체。이용 X사선연사광보(X-ray Diffraction, XRD)、소묘전경(Scanning Electron Microscope, SEM)급홍외(Fourier Transform Infrared, FT-IR)보의대제비고화체적물상、결구화미관형모진행분석표정,병대기항침출성능화복조성능진행료연구。결과표명,당 x<0.5시,고화체위단일물상;당 x≥0.5시,고화체중출현제이상。고화체중적 Sr2+、Zr4+적침출농도수침포시간이증대,재침포42 d 시,Sr2+적최대침출농도위0.0065μg.mL?1,Zr4+적최대침출농도위0.01μg.mL?1。
Background: 90Zr is a decay product of 90Sr, which may induce structural changes of radioactive waster forms. Purpose: In order to study the influence of decay product on the stability of perovskite-type SrTiO3 used for immobilizing 90Zr, C4H6O4Sr.0.5H2O, TiO2 and ZrOCl2.8H2O are used as the starting materials. Methods: The Zr-doped SrTiO3 synthesized can be generally represented as SrZrxTi1?xO3 (0≤x<1) with the high temperature solid reaction. The phases, structure and microcosmic shape of synthetic condensates were characterized by the X-ray Diffraction (XRD), Scanning Electron Microscope (SEM) and Fourier Transform Infrared (FT-IR), and long-term chemical stability was studied at constant temperature of 90 oC. Results: The results indicate that the second phase of compounds is observed when the value of x is more than 0.5. The leaching rate of Sr2+ and Zr4+ in waste forms increase with the immersion time, while the highest leaching ratios for 42 d are no more than 0.006 5 μg.mL?1 and 0.01 μg.mL?1, respectively. The crystalline phase and morphology of solidified SrZrxTi1?xO3 waste form are influenced by electron beam irradiation. Conclusion: This study results may provide technical support for long-time immobilization of the 90Sr.