氚纯化装置的研制及性能验证研究
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摘要
铀是一种传统的贮氚材料,在铀粉瓶中贮存的氚会不断衰变产生氦气,导致使用时氚的纯度下降,影响标记化合物产率。本研究设计了氚纯化装置,对装置进行安装调试,并对该装置中的铀床进行活化,利用该装置测定铀吸收氘单质气体的p-t曲线及在400~550℃范围的解吸氘气体的p-t曲线。应用调试好的系统对长期存放贮氚铀粉瓶中的氚进行纯化。结果表明,设计的氚纯化装置系统密封性好,经氦质谱检漏测定值为7.8×10~(-13 )Pa·m~3/s;利用该装置测定氘的吸附饱和曲线,氘完全解吸时铀对氘的吸附量为240mL/g。验证实验回收了久置铀粉瓶中的氚为1.44×10~(13 )Bq,利用氦气体积推算出久置铀粉瓶中含氚质量百分率为53.1%。实验结果证实了系统纯化氚的可行性,可为氚标记化合物制备提供可靠的氚源。
Tritium labeled compounds play an important role in new drug research,including the characteristics of absorption,distribution,metabolism and excretion.Uranium is a traditional tritium storage material.The constant decay of tritium in the uranium bed could produce helium which could reduce the purity of tritium and lead to affect the yield of the preparation reaction of labeled compounds.A tritium device was designed and installed in this study.The system debugging and purification of the tritium in the long stored uranium bed were also carried out.After a series of performance test,the p-t curves of deuterium absorption by uranium and p-t curves of desorption(between 400-500℃)were measured.The results show that the system has good tightness and the value is 7.8×10~(-13 )Pa·m~3/s of leak detection by helium mass-spectrometer leak detector.According to pressure calculation,the adsorption amount of uranium to deuterium is 240mL/g.The verification experiment reclaimed the tritium 1.44×10~(13 )Bq and calculated the mass percentage of tritium is 53.1%by the volume of helium gas.It is confirmed the feasibility of tritium purification by the system.It has important practical significance and provides reliable tritium gas for the preparation of labeled compounds.
Tritium labeled compounds play an important role in new drug research,including the characteristics of absorption,distribution,metabolism and excretion.Uranium is a traditional tritium storage material.The constant decay of tritium in the uranium bed could produce helium which could reduce the purity of tritium and lead to affect the yield of the preparation reaction of labeled compounds.A tritium device was designed and installed in this study.The system debugging and purification of the tritium in the long stored uranium bed were also carried out.After a series of performance test,the p-t curves of deuterium absorption by uranium and p-t curves of desorption(between 400-500℃)were measured.The results show that the system has good tightness and the value is 7.8×10~(-13 )Pa·m~3/s of leak detection by helium mass-spectrometer leak detector.According to pressure calculation,the adsorption amount of uranium to deuterium is 240mL/g.The verification experiment reclaimed the tritium 1.44×10~(13 )Bq and calculated the mass percentage of tritium is 53.1%by the volume of helium gas.It is confirmed the feasibility of tritium purification by the system.It has important practical significance and provides reliable tritium gas for the preparation of labeled compounds.
引文
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[3] DO Energy.Tritium handing and safe storage,DOE-HEBK-1129-2007[R]. Washington DC:USDOE,2007.
[4] Bloch J.The hydriding kinetis of activated uranium powder under low(near equilibrium)hydrogen pressure[J].J Alloy Compd,2003,361:130.
[5]于宁文,陈宝军,向学琴,等.一种氚气纯化系统:中国,ZL 201520926520.5[P].2016-05-04.
[6]达道安.真空设计手册(第3版)[M].北京:国防工业出版社,2004.
[7]中华人民共和国家质量监督检验检疫总局,中国国家标准化管理委员会.GB/T 32218-2015真空技术真空系统漏率测试方法[S].北京:中国标准出版社,2015.
[8]蒋国强,罗德礼,陆光达,等.氚和氚的工程技术[M].北京:国防工业出版社,2007.