目的:探讨24 h摄碘率(24 h RAIU)对^(131)I治疗甲状腺功能亢进(简称甲亢)的效果及体内残留活度的影响。方法:选取2017年6月-2022年6月白银市第一人民医院收治的50例Graves甲亢患者作为研究对象,根据患者治疗前24 h RAIU的不同分为Ⅰ组(2...目的:探讨24 h摄碘率(24 h RAIU)对^(131)I治疗甲状腺功能亢进(简称甲亢)的效果及体内残留活度的影响。方法:选取2017年6月-2022年6月白银市第一人民医院收治的50例Graves甲亢患者作为研究对象,根据患者治疗前24 h RAIU的不同分为Ⅰ组(24 h RAIU<50%)、Ⅱ组(50%≤24 h RAIU≤80%)、Ⅲ组(24 h RAIU>80%)。患者均采用^(131)I治疗,比较三组治疗效果及治疗后72 h体内残留^(131)I活度。结果:Ⅰ组治疗总有效率最高,其次为Ⅱ组,Ⅲ组最低,差异有统计学意义(P<0.05)。Ⅰ组治疗后72 h体内残留^(131)I活度最低,其次为Ⅱ组,Ⅲ组最高,差异有统计学意义(P<0.05)。结论:24 h RAIU可影响甲亢患者^(131)I治疗效果和72 h体内残留^(131)I活度,24 h RAIU越大,治疗有效率越低,72 h体内残留^(131)I活度越高。展开更多
The production of radionuclides(90)^Sr and(131)^I in molten salt reactors is an attractive option to address the global shortage of radionuclides.This study evaluated the production characteristics of(90)^Sr and(131)^...The production of radionuclides(90)^Sr and(131)^I in molten salt reactors is an attractive option to address the global shortage of radionuclides.This study evaluated the production characteristics of(90)^Sr and(131)^I in a modular molten salt reactor,such as equilibrium time,yield,and cooling time of isotopic impurities.The fuel burn-up of a small modular molten salt reactor was analyzed by the Triton module of the scale program,and the variation in the fission yields of the two nuclides and their precursors with burn-up time.The yield of(131)^I and~(131)Te has been increasing during the lifetime.131 I has an equilibrium time of about 40 days,a saturation activity of about 40,300 TBq,and while~(131)Te takes 250 min to reach equilibrium,the equilibrium activity was about 38,000 TBq.The yields of90 Sr and~(90)Kr decreased gradually,the equilibrium time of90 Kr was short,and(90)^Sr could not reach equilibrium.Based on the experimental data of molten salt reactor experiment,the amount of nuclide migration to the tail gas and the corresponding cooling time of the isotope impurities under different extraction methods were estimated.Using the HF-H_2 bubbling method,3.49×10^(5)TBq of(131)^I can be extracted from molten salt every year,and after13 days of cooling,the impurity content meets the medical requirements.Using the electric field method,1296 TBq of(131)^I can be extracted from the off-gas system(its cooling time is 11 days)and 109 TBq of(90)^Sr.The yields per unit power for(131)^I and(90)^Sr is approximately 1350 TBq/MW and 530 TBq/MW,respectively,which shows that molten salt reactors have a high economic value.展开更多
文摘目的:探讨24 h摄碘率(24 h RAIU)对^(131)I治疗甲状腺功能亢进(简称甲亢)的效果及体内残留活度的影响。方法:选取2017年6月-2022年6月白银市第一人民医院收治的50例Graves甲亢患者作为研究对象,根据患者治疗前24 h RAIU的不同分为Ⅰ组(24 h RAIU<50%)、Ⅱ组(50%≤24 h RAIU≤80%)、Ⅲ组(24 h RAIU>80%)。患者均采用^(131)I治疗,比较三组治疗效果及治疗后72 h体内残留^(131)I活度。结果:Ⅰ组治疗总有效率最高,其次为Ⅱ组,Ⅲ组最低,差异有统计学意义(P<0.05)。Ⅰ组治疗后72 h体内残留^(131)I活度最低,其次为Ⅱ组,Ⅲ组最高,差异有统计学意义(P<0.05)。结论:24 h RAIU可影响甲亢患者^(131)I治疗效果和72 h体内残留^(131)I活度,24 h RAIU越大,治疗有效率越低,72 h体内残留^(131)I活度越高。
基金supported by the Strategic Priority Research Program of the Chinese Academy of Sciences(No.XDA02010000)Thorium Uranium Fuel Cycle Characteristics and Key Problem Research Project(No.QYZDY-SSW-JSC016)Shanghai Natural Science Foundation(No.19ZR1468000)。
文摘The production of radionuclides(90)^Sr and(131)^I in molten salt reactors is an attractive option to address the global shortage of radionuclides.This study evaluated the production characteristics of(90)^Sr and(131)^I in a modular molten salt reactor,such as equilibrium time,yield,and cooling time of isotopic impurities.The fuel burn-up of a small modular molten salt reactor was analyzed by the Triton module of the scale program,and the variation in the fission yields of the two nuclides and their precursors with burn-up time.The yield of(131)^I and~(131)Te has been increasing during the lifetime.131 I has an equilibrium time of about 40 days,a saturation activity of about 40,300 TBq,and while~(131)Te takes 250 min to reach equilibrium,the equilibrium activity was about 38,000 TBq.The yields of90 Sr and~(90)Kr decreased gradually,the equilibrium time of90 Kr was short,and(90)^Sr could not reach equilibrium.Based on the experimental data of molten salt reactor experiment,the amount of nuclide migration to the tail gas and the corresponding cooling time of the isotope impurities under different extraction methods were estimated.Using the HF-H_2 bubbling method,3.49×10^(5)TBq of(131)^I can be extracted from molten salt every year,and after13 days of cooling,the impurity content meets the medical requirements.Using the electric field method,1296 TBq of(131)^I can be extracted from the off-gas system(its cooling time is 11 days)and 109 TBq of(90)^Sr.The yields per unit power for(131)^I and(90)^Sr is approximately 1350 TBq/MW and 530 TBq/MW,respectively,which shows that molten salt reactors have a high economic value.
