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中国原子能科学研究院 北京 102413
[ "聂鹏, 男, 1980年出生, 2010年于中国原子能科学研究院获硕士学位, 现为博士研究生", "NIE Peng, male, born in 1980, graduated from China Institute of Atomic Energy with a master's degree in 2010, doctoral student" ]
收稿日期:2017-05-15,
修回日期:2017-06-29,
纸质出版日期:2017-11-10
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聂鹏. 反应堆石墨中14C生成及滞留机制的分析和探讨[J]. 核技术, 2017,40(11):110606
Peng NIE. Study on production and retention of 14C in thermal column graphite of HWRR[J]. Nuclear techniques, 2017, 40(11): 110606
聂鹏. 反应堆石墨中14C生成及滞留机制的分析和探讨[J]. 核技术, 2017,40(11):110606 DOI: 10.11889/j.0253-3219.2017.hjs.40.110606.
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.
14
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
14
C生成机制复杂,主要来源于
13
C、
14
N、
17
O分别与中子发生的三个反应:
13
C(n,γ)
14
C、
14
N(n,p)
14
C、
17
O(n,α)
14
C,重水研究堆石墨中由
14
N(n,p)反应生成的
14
C约占
14
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
14
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
2
,后者生成的
14
C以热原子形式存在,并迅速与O
2
结合生成
14
CO
2
,发现了反应堆停闭后石墨孔隙闭孔中依然存在
14
CO
2
,并估算了以孔隙
14
CO
2
形式存在的
14
C约占石墨中
14
C总量的30%。
Background
2
Having a half-life of 5 730 a
14
C is the radionuclide of greatest concern in nuclear graphite
which arises principally through the interaction of reactor neutrons with nitrogen
via
14
N(n
p) reaction.
Purpose
2
This study aims to propose a mechanism for the production and retention of
14
C in graphite and needs to be verified.
Methods
2
The specific activities for
14
C have been calculated and experimentally determined. Nitrogen exists in heavy water research reactor (HWRR) graphite in two forms:impurity N and interstice N
2
. A comparison between
14
C specific activities in ground and unground graphite samples has been done.
Results
2
The
14
C atoms produced by the interstice N
2
usually exist in "hot atom" state and immediately form
14
CO
2
part of which may resides in graphite and the other part may eventually escape to air.
Conclusion
2
A comparison between
14
C specific activities in ground and unground graphite samples reveals that the interstice
14
CO
2
accounts for 30% approximately of total
14
C in the thermal column graphite of heavy water research reactor.
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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