Study on production and retention of <sup>14</sup>C in thermal column graphite of HWRR

Peng NIE

doi:10.11889/j.0253-3219.2017.hjs.40.110606

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Study on production and retention of ¹⁴C in thermal column graphite of HWRR

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Study on production and retention of ¹⁴C in thermal column graphite of HWRR
- NUCLEAR TECHNIQUES Vol. 40, Issue 11, Article number: 110606(2017)
- 作者机构：
  
  中国原子能科学研究院北京 102413
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2017.hjs.40.110606
  CLC： O571.5
- Received：15 May 2017，
  
  Revised：29 June 2017，
  
  Published：10 November 2017
- 稿件说明：
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Peng NIE. Study on production and retention of ¹⁴C in thermal column graphite of HWRR[J]. Nuclear techniques, 2017, 40(11): 110606
DOI：

Peng NIE. Study on production and retention of ¹⁴C in thermal column graphite of HWRR[J]. Nuclear techniques, 2017, 40(11): 110606 DOI： 10.11889/j.0253-3219.2017.hjs.40.110606.

摘要

C是退役石墨中最重要的核素，半衰期为5730 a，处理处置过程需要重点关注。石墨中

C生成机制复杂，主要来源于

C、

N、

O分别与中子发生的三个反应：

C（n，γ）

C、

N（n，p）

C、

O（n，α）

C，重水研究堆石墨中由

N（n，p）反应生成的

C约占

C总量的90%以上。本文通过理论计算和实验比较方法对反应堆热柱石墨中

C生成及滞留机制进行了分析和探讨，得出了石墨中N来源于杂质N和孔隙N

，后者生成的

C以热原子形式存在，并迅速与O

结合生成

，发现了反应堆停闭后石墨孔隙闭孔中依然存在

，并估算了以孔隙

形式存在的

C约占石墨中

C总量的30%。

Abstract

Background

Having a half-life of 5 730 a

C is the radionuclide of greatest concern in nuclear graphite

which arises principally through the interaction of reactor neutrons with nitrogen

via

N(n

p) reaction.

Purpose

This study aims to propose a mechanism for the production and retention of

C in graphite and needs to be verified.

Methods

The specific activities for

C have been calculated and experimentally determined. Nitrogen exists in heavy water research reactor (HWRR) graphite in two forms:impurity N and interstice N

. A comparison between

C specific activities in ground and unground graphite samples has been done.

Results

The

C atoms produced by the interstice N

usually exist in "hot atom" state and immediately form

part of which may resides in graphite and the other part may eventually escape to air.

Conclusion

A comparison between

C specific activities in ground and unground graphite samples reveals that the interstice

accounts for 30% approximately of total

C in the thermal column graphite of heavy water research reactor.

关键词

Keywords

references

IAEA-TECDOC-1521. Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors[R]. Vienna:IAEA, 2006

IAEA-TECDOC-1647. Progress in radioactive graphite waste management[R]. Vienna:IAEA, 2000

X L Hou . Rapid analysis of 14 C and 3 H in graphite and concrete for decommissioning of nuclear reactor . Applied Radiation and Isotopes , 2005 . 62 871 - 882 . DOI: 10.1016/j.apradiso.2005.01.008 http://doi.org/10.1016/j.apradiso.2005.01.008 .

杨怀元 , 王治惠 , 刘卫 , . 反应堆退役废物中 3 H, 14 C, 36 Cl, 63 Ni和 55 Fe的液闪计数测量 . 原子能科学技术 , 1996 . 30 ( 6 ): 509 - 515 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS606.006.htm .

Huaiyuan YANG , Zhihui WANG , Wei LIU , . Activity determination of 3 H, 14 C, 36 Cl, 63 Ni and 55 Fe in solid wastes from decommissioned reactor using liquid scintillation counting (LSC) . Atomic Energy Science and Technology , 1996 . 30 ( 6 ): 509 - 515 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS606.006.htm .

邱永梅 , 王萍 , 但贵萍 , . 反应堆退役石墨中 14 C分析制样实验系统研制 . 原子能科学技术 , 2009 . 44 119 - 123 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2010S1026.htm .

Yongmei QIU , Ping WANG , Guiping DAN , . Development on analysis and making sample experiment system of 14 C in graphite in decommissioning of reactor . Atomic Energy Science and Technology , 2009 . 44 119 - 123 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2010S1026.htm .

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Related Institution

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Study on production and retention of 14C in thermal column graphite of HWRR

DOI：10.11889/j.0253-3219.2017.hjs.40.110606

摘要

Abstract

关键词

Keywords

references

Study on production and retention of ¹⁴C in thermal column graphite of HWRR