首页 | 本学科首页   官方微博 | 高级检索  
文章检索
  按 检索   检索词:      
出版年份:   被引次数:   他引次数: 提示:输入*表示无穷大
  收费全文   33篇
  免费   0篇
化学   13篇
物理学   20篇
  2017年   1篇
  2016年   5篇
  2015年   2篇
  2014年   1篇
  2012年   2篇
  2008年   1篇
  1994年   7篇
  1993年   4篇
  1992年   5篇
  1991年   2篇
  1990年   3篇
排序方式: 共有33条查询结果,搜索用时 15 毫秒
11.
12.
177Lu-labeled receptor avid peptides and monoclonal antibodies have been effectively used in targeted tumor therapy, owing to the ideally suited decay properties and favourable production logistics of 177Lu [T½ = 6.65 days; Eβ(max) = 497 keV (78.6 %); Eγ = 208 keV (11.0 %)]. The specific activity of 177Lu produced by the (n,γ) route is one of the important criteria, which determines the efficacy of 177Lu-labeled receptor-avid biomolecules. The present article highlights that the specific activity of (n,γ) produced 177Lu cannot be calculated by simply dividing the produced activity by the mass of the target irradiated, unlike other (n,γ) produced medical radioisotopes and there is a significant enhancement of specific activity due to the burn up of the Lu target during irradiation, which is an added advantage towards the utilization of 177Lu in receptor specific therapeutic radiopharmaceuticals.  相似文献   
13.
14.
15.
16.
17.
18.
19.
20.
Trace metallic impurity analysis by spectroscopic techniques is one of the important steps of chemical quality control of nuclear fuel materials. Depending on the burn-up and the storage time of the fuel, there is an accumulation of 241Am in plutonium based fuel materials due to β decay of 241Pu. In this paper, attempts were made to develop a method for separation of 241Am from 1.2 kg of analytical solid waste containing 70% U, 23% Pu, 5% Ag and 1–2% C as major constituents along with other minor constituents generated during trace metal assay of plutonium based fuel samples by d. c. arc carrier distillation atomic emission spectrometry. A combination of ion exchange, solvent extraction and precipitation methods were carried out to separate ~45 mg of 241Am as Am(NO3)3 from 15 L of the analytical waste solution. Dowex 1×4 ion exchange chromatographic method was used for separation of Pu whereas 30% TBP–kerosene was utilized for separation of U. Am was separated from other impurities by fluoride precipitation followed by conversion to nitrate. The recovery of Pu from ion exchange chromatographic separation step was ~93% while the cumulative recovery of Am after separation process was found to be ~90%.  相似文献   
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号