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从高放废液中去除超铀元素的TRPO流程热实验 被引量:12

Hot tests of the TRPO process for the removal of TRU elements from HLLW
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摘要 阐述了从高放废液中去除超铀元素的TRPO流程热实验。热实验是用真实动力堆的 高放液进行的,取得了很好的效果。超铀元素镅、镎、钚和铀的去污系数分别大于 3 000,4 000, 950和 7 000。 TRPO流程在去除超铀元素的同时,还能去除对放射性废物长期危害起决定作用 的99Tc。实验结果表明TRPO流程具有去污效率高,反萃效果好,锕系组分之间交叉污染小和试 剂成本低等诸多优点。TRPO流程是一个有效的从高放废液中去除超铀元素的流程。 The hot tests of the TRPO process for the removal of transuranium elements (TRU) from high level liquid waste (HLLW) were undertaken with real HLLW in hot cell. Very good results have been obtained. The decontamination factors D. are higher than 3 000, 4 000, 7 000 and 950 for americium, neptunium, uranium and plutonium respectively. In the meantime, the TRPO process could also remove 99Tc, which is a key element responsible for the long term risk of the radioactive waste. The hot tests results show that the TRPO process has good D. and excellent stripping efficiency for TRU elements and 99 Tc, as well as very low cross contamination of TRU elements between different process streams. The TRPO process is an effective and perspective for removing TRU elements from HLLW.
出处 《清华大学学报(自然科学版)》 EI CAS CSCD 北大核心 1996年第6期102-110,共9页 Journal of Tsinghua University(Science and Technology)
关键词 超铀元素 TRPO流程 放射性废物 高放废液 处理 HLLW TRU element hot test TRPO process
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参考文献6

  • 1宋崇立,The Fourth International Conf on Nuclear Fuel Reporcessing and Waste Management,1994年
  • 2宋崇立,核化学与放射化学,1992年,14卷,193页
  • 3宋崇立,核科学与工程,1992年,12卷,225页
  • 4Zhu Y J,Transuranium element,a half century,1992年
  • 5陈建峰,清华大学学报,1988年,28卷,增2期,10页
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