基于氢研究核石墨中氚的去除

邓珂; 马玉华; 秦来来; 刘佳煜; 张钦; 马兆伟; 杨果; 卫飞; 吴喜军; 王广华; 刘卫

doi:10.11889/j.0253-3219.2018.hjs.41.050502

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基于氢研究核石墨中氚的去除

核物理、交叉学科研究 | 更新时间：2021-05-19

- 基于氢研究核石墨中氚的去除
- Tritium removal from nuclear graphite base on hydrogen study
- 核技术 2018年41卷第5期文章编号：050502
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院大学北京 100049
  3.南华大学数理学院衡阳 421001
- 作者简介：
  
  [ "邓珂, 男, 1990年出生, 2015年毕业于英国伦敦帝国理工学院, 现为博士研究生, 研究方向为退役核石墨中氚的去污工艺研究", "DENG Ke, male, born in 1990, graduated from London Imperial College in 2015, doctoral student, focusing on the removal of tritium from irradiated nuclear graphite" ]
  刘卫, E-mail:liuwei@sinap.ac.cn LIU Wei, E-mail:liuwei@sinap.ac.cn
- 基金信息：
- DOI：10.11889/j.0253-3219.2018.hjs.41.050502
  中图分类号： TL271
- 收稿日期：2018-01-22，
  
  修回日期：2018-02-05，
  
  纸质出版日期：2018-05-10
- 稿件说明：
移动端阅览
邓珂, 马玉华, 秦来来, 等. 基于氢研究核石墨中氚的去除[J]. 核技术, 2018,41(5):050502

Ke DENG, Yuhua MA, Lailai QIN, et al. Tritium removal from nuclear graphite base on hydrogen study[J]. Nuclear techniques, 2018, 41(5): 050502
邓珂, 马玉华, 秦来来, 等. 基于氢研究核石墨中氚的去除[J]. 核技术, 2018,41(5):050502 DOI： 10.11889/j.0253-3219.2018.hjs.41.050502.

Ke DENG, Yuhua MA, Lailai QIN, et al. Tritium removal from nuclear graphite base on hydrogen study[J]. Nuclear techniques, 2018, 41(5): 050502 DOI： 10.11889/j.0253-3219.2018.hjs.41.050502.

摘要

世界现阶段有大量的退役核石墨需要处理，

H和

C为其中含量最多、需重点去污核素。对于

C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

C。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℃的吸附以及400~700℃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

，其中化学吸附量分别为3.2×10

-3

mL·g

-1

、3.0×10

-3

mL·g

-1

和0.92×10

-3

mL·g

-1

。石墨对氢吸附量上的差异可能来源于三种核石墨的不同制备工艺和物理性质上的一些差异，这些差异主要来自于平均孔径、比表面积、成型工艺以及焦粒粒径上的区别；NG-CT-10有效吸附量所占比最高，表明NG-CT-10有较大量的氚吸附量。400~700℃的核石墨氢解吸实验表明：三种石墨中的氢主要是从700℃开始有效解吸，但各自相对于总吸附量的解吸量有明显区别，NG-CT-10、IG-110和NBG-18在700℃时的解吸量分别为7%、13.5%和70%。由此可得，NBG-18中的氚最易被解吸出来。根据氢在石墨中的吸附模型，700℃解吸出来的氢应该位于石墨晶粒边缘。为了解吸剩余氚，同时不影响

C的有效去除，不提高热处理温度，可能需要改变解吸时的载气组分。

Abstract

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

C are the two main radionuclides that should be specially treated before final disposal. The optimal desorption temperature for

C was reported to be 700℃.

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 of hydrogen at 350℃ and desorption of hydrogen from 400℃ to 700℃ in three types of nuclear graphite.

Methods

Samples of three types of nuclear graphite were subjected to flowing hydrogen at 350℃ for hydrogen absorption

then the absorbed hydrogen was desorbed by thermal treatment from 400℃ to 700℃. The hydrogen concentration of the outlet gas was measured by gas chromotagraph.

Results

According to our experiments

three types of nuclear graphite have different amount of absorption

but the following desorption experiments showed similar trend with some differences on the amount of desorption varied with time. The amount of absorption of the domestic nuclear graphite NG-CT-10

Japanese nuclear graphite IG-110 and Germen nuclear graphite NBG-18 were measured to be 6.7×10

-3

mL·g

-1

9.3×10

-3

mL·g

-1

and 9.12×10

-3

mL·g

-1

respectively

and the amount of hydrogen that is chemically absorbed in graphite were 3.2×10

-3

mL·g

-1

3.0×10

-3

mL·g

-1

and 0.92×10

-3

mL·g

-1

respectively. The difference in the amount of absorption could be due to the difference in the physical properties and synthetic process. Moreover

the absorbed hydrogen start to desorb effectively after the temperature was raised to 700℃. For the three types of nuclear graphite investigated in our research

the amount of desorption at 700℃ was different:7% of hydrogen was desorbed in NG-CT-10 graphite

13.5% for IG-110 and 70% for NBG-18 nuclear graphite.

Conclusion

Based on our findings

the amount of stability absorbed hydrogen in domestic nuclear graphite NG-CT-10 was the highest

hence amount of tritium absorbed could also be the highest in NG-CT-10 nuclear graphite. According to the model of hydrogen absorption in nuclear graphite proposed by Atsumi

the hydrogen desorbed at 700℃ were the hydrogen absorbed at the edge surface of graphite crystallites. To fully desorb tritium and

C effectively at 700℃

the carrier gas during desorption should be varied.

关键词

Keywords

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