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Design and simulation study of an online activity monitoring device for radioactive noble gases in thorium molten salt reactor
- NUCLEAR TECHNIQUES Vol. 48, Issue 11, Article number: 110401(2025)
- 作者机构：
1.中国科学院上海应用物理研究所 上海 201800
2.中国科学院大学 北京 100049
- 作者简介：
LIAO Chuan, male, born in 2001, graduated from Chengdu University of Technology in 2023, master student, focusing on application of nuclear technology
ZHOU Xuemei, E-mail: zhouxuemei@sinap.ac.cn
- 基金信息：
DOI：10.3724/j.0253-3219.2025.hjs.48.250116
CLC： TL814Received：19 March 2025，
Revised：2025-06-07，
Published：15 November 2025
- 稿件说明：
移动端阅览
廖川,周雪梅,廖峰等.钍基熔盐堆中放射性惰性气体在线监测装置的设计与模拟研究[J].核技术,2025,48(11):110401.
LIAO Chuan,ZHOU Xuemei,LIAO Feng,et al.Design and simulation study of an online activity monitoring device for radioactive noble gases in thorium molten salt reactor[J].NUCLEAR TECHNIQUES,2025,48(11):110401.
廖川,周雪梅,廖峰等.钍基熔盐堆中放射性惰性气体在线监测装置的设计与模拟研究[J].核技术,2025,48(11):110401. DOI： 10.3724/j.0253-3219.2025.hjs.48.250116. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.250116.
LIAO Chuan,ZHOU Xuemei,LIAO Feng,et al.Design and simulation study of an online activity monitoring device for radioactive noble gases in thorium molten salt reactor[J].NUCLEAR TECHNIQUES,2025,48(11):110401. DOI： 10.3724/j.0253-3219.2025.hjs.48.250116. CSTR： 32193.14.hjs.CN31-1342/TL.2025.48.250116.
摘要
钍基熔盐堆在运行过程中会排放
85
Kr和
133
Xe等放射性惰性气体（特征核素），准确监测尾气出口处各特征核素活度浓度对了解核反应堆与尾气处理系统的运行状况具有重要意义。β-γ符合法可显著降低本底且提高测量精度，能满足监测需求，因此，设计了由高纯锗（High-Purity Germanium，HPGe）和钝化注入平面硅（Passivated Implanted Planar Silicon，PIPS）组成的符合监测装置。基于熔盐堆尾气中的核素活度浓度理论值，使用MCNP（Monte Carlo N Particle Transport Code）设计了采样腔最佳尺寸，研究了探测器对β和γ探测效率的影响，并使用Geant4（GEometry ANd Tracking 4）分析了监测系统在HPGe下γ射线能谱与β-γ符合分析后的γ射线能谱及最小可探测活度浓度（Minimum Detectable Concentration，MDC）。结果表明：圆柱体型的采样腔最佳尺寸高5.3 cm，半径4.25 cm，该监测装置具备核素识别能力且特征核素的MDC为1~10
3
mBq·m
-3
，性能较为优异。本文结果可为后续监测装置的加工与测试提供理论依据。
Abstract
Background
2
In normal operation
Thorium Molten Salt Reactor (TMSR) can produce radioactive noble gases such as Argon
Krypton and Xenon. They are expelled into the environment
via
the exhaust outlet after a desorption treatment. The accurate identification and measurement of the activity levels of different inert gases in exhaust emissions provide critical insights for assessing the operational status of nuclear reactors and associated off-gas treatment systems.
Purpose
2
This study aims to develop a coincidence monitoring device to identify nuclides and measure the radioactivity of noble gases in online model of TMSR.
Methods
2
A sampling chamber
an inner 50 mm diameter Passivated Implanted Planar Silicon (PIPS) and an ORTEC P-type coaxial high-purity germanium detector were applied to the monitoring device
and a 300 mL sampling chamber was taken as the baseline. Then
Monte Carlo N Particle Transport Code (MCNP) simulations were conducted to evaluate the detection efficiencies for four characteristic radionuclides
as well as to investigate the influence of the distance between the HPGe detector and the chamber on gamma-ray detection efficiency
thus determining the optimal chamber dimensions. Finally
the Geant4 code was employed to analyze the gamma spectra of characteristic nuclides
as well as the gamma spectra following β-γ coincidence. Furthermore
the minimum detectable concentrations (MDCs) for four characteristic nuclides were calculated based on this model.
Results
2
The simulation results show that the sampling chamber is optimized with dimensions of 5.3 cm in height and 4.25 cm in radius
while maintaining a 5 cm separation distance between the HPGe and the chamber. The monitoring device demonstrates levels of MDC ranging from 1 mBq·m
-3
to 10
3
mBq·m
-3
for four characteristic radionuclides.
Conclusions
2
Simulation results of the coincidence monitoring device designed in this study demonstrate its capability to detect and identify various noble gases. Benchmarking these performance metrics against empirical calibration data constitutes a critical validation step for assessing the system's operational reliability.
关键词
Keywords
references
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