Sample preparation system of 14C in the main materials of nuclear reactor

QIU Yongmei; DAN Guiping; WEN Wei; TAN Zhaoyi; ZENG Junhui; SUN Yu; FAN Yingwu

doi:10.11889/j.0253-3219.2015.hjs.38.050302

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Sample preparation system of 14C in the main materials of nuclear reactor

更新时间：2021-03-03

- Sample preparation system of 14C in the main materials of nuclear reactor
- NUCLEAR TECHNIQUES Vol. 38, Issue 5, Article number: 050302(2015)
- 作者机构：
  
  中国工程物理研究院核物理与化学研究所,绵阳,621900
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2015.hjs.38.050302
  CLC：
- Published：08 May 2015
- 稿件说明：
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QIU Yongmei, DAN Guiping, WEN Wei, et al. Sample preparation system of 14C in the main materials of nuclear reactor[J]. Nuclear techniques, 2015, 38(5): 050302
DOI：

QIU Yongmei, DAN Guiping, WEN Wei, et al. Sample preparation system of 14C in the main materials of nuclear reactor[J]. Nuclear techniques, 2015, 38(5): 050302 DOI： 10.11889/j.0253-3219.2015.hjs.38.050302.

摘要

为了分析测量退役反应堆堆材料中的14C活度，需要克服材料中14C制样的难点，基于智能化自动控制原理，研制一套14C制样系统。系统主要由缓冲器、解析室、催化床、吸附床和吸收床等部件构成。将样品在高温下有氧的气氛中完全分解，并将生成的气体通过催化氧化成CO2，用乳化闪烁液的固体悬浮法在液闪谱仪上测量14C放射性活度。研究结果表明，该方法对14C的探测限为0.0331Bq?g?1（石墨）和0.0218Bq?g?1（混凝土），全程加标回收率大于70%；整套仪器稳定性良好，能实现对反应堆堆本体材料中低浓度石墨和混凝土样品的制备，准确给出材料中14C活度，为反应堆退役提供重要数据参考。

Abstract

Background: The sample preparation system of 14C is necessary for measuring the radioactive contents of 14C and 3H for the decommissioning of nuclear reactor. Previous works were concentrated on the glass container and heating furnace which is not suitable for automatic sample process and exists safety risk. Purpose: In order to resolve the difficulty in main materials of nuclear reactor samples preparation of 14C

an intellectual preparation system of 14C samples was designed and developed. Methods: The system is designed to consist of buffer

decomposition chamber

catalysis bed

adsorption bed and absorbing bed. Samples were decomposed at high temperature in oxygen whilst the generated gas was translated to CO2 by catalysis oxidation. The activity of 14C was measured by liquid scintillation counter using suspension method. Results: The radiochemical recovery rate of 14C was above 70%. The calculated detection limit for 14C was 0.033 1 Bq?g?1 for graphite and 0.021 8 Bq?g?1 for concrete

respectively. Conclusion: This system was stable enough to be used for preparing graphite and concrete samples which contain low level or medium level radioactivity in nuclear reactor. Abstract

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