期刊论文

Tritium removal from nuclear graphite base on hydrogen study

Liu, W.

中文

核技术

0253-3219

2018

41

5

61-67

10.11889/j.0253-3219.2018.hjs.41.050502

本校为其他机构

世界现阶段有大量的退役核石墨需要处理,3H和14C为其中含量最多、需重点去污核素。对于14C来说,低温(不高于700 ℃)低氧环境下的热处理能比较有选择性地去除核石墨中的14C。基于氚是氢的同位素、与氢具有相同的物理化学特性,本研究通过对三种不同产地的核石墨中氢在350 ºC的吸附以及400~700 ºC的解吸行为,探究核石墨中氚的去污工艺。实验发现:三种核石墨的氢吸附量不同,解吸规律大致相同,解吸量随时间的变化上有差异。国产核石墨NG-CT-10、日本核石墨IG-110以及德国核石墨NBG-18的氢总吸附量分别为6.7×10~(–3) mL·g~(–1)、9.30×10~(–3) mL·g~(–1)以及9.12×10~(–3) mL·g~(–1),其中...

[Background] Nowadays, there are big amount of irradiated nuclear graphite waiting to be decomissioned worldwide. Due to their high content in nuclear graphite, tritium and 14C are the two main radionuclides that should be specially treated before final disposal. The optimal desorption temperature for 14C was reported to be 700 °C. [Purpose] As tritium is the isotope of hydrogen with similar physical and chemical properties, in order to investigate the desorption process for tritium in nuclear graphite, this study investigates the absorption o...