基于源活度反演计算的γ辐射场数据重构方法

李华, 赵原, 曹勤剑, 何良, 李君利, 刘立业

清华大学学报(自然科学版) ›› 2020, Vol. 60 ›› Issue (10) : 880-886.

PDF(2582 KB)
PDF(2582 KB)
清华大学学报(自然科学版) ›› 2020, Vol. 60 ›› Issue (10) : 880-886. DOI: 10.16511/j.cnki.qhdxxb.2020.25.014
工程物理

基于源活度反演计算的γ辐射场数据重构方法

  • 李华1, 赵原1, 曹勤剑1, 何良1,2, 李君利2, 刘立业1
作者信息 +

γ-radiation field reconstruction method basedon source activity inversion calculations

  • LI Hua1, ZHAO Yuan1, CAO Qinjian1, HE Liang1,2, LI Junli2, LIU Liye1
Author information +
文章历史 +

摘要

三维辐射场是反映核设施内真实外照射分布的重要数据库,可为核设施现场建立有效的屏蔽措施及确定合理的作业方案提供数据基础。为了重构出与实际较为相符的三维γ辐射场,结合点核积分理论,该文利用最小二乘法和Gauss-Seidel迭代算法,建立了基于源活度反演计算的γ辐射场重构方法,研究了所选取测量点位置对源活度反演结果的影响,并结合某核电现场的实地测量数据对该重建方法进行了实验验证与计算分析。结果表明:在现场实验中基于源活度反演算法重构出的γ辐射场数据与相对应的测量数据之间的偏差约为10%,能够满足核设施现场辐射防护的计算需要,可为其现场的辐射防护最优化提供技术支持。

Abstract

Three-dimensional radiation fields must be known to predict the distribution of real external exposures in nuclear facilities. Such data fields provide the basis for establishing effective shielding measures and determining reasonable operating plans at nuclear facilities. Three-dimensional gamma radiation fields were reconstructed using point-kernel integral theory and a source activity inversion algorithm using the least squares method and a Gauss-Seidel iterative algorithm. The results were then used to study the influences of the dose measurement positions on the source inversion results. The reconstruction method was verified using measured data from a nuclear power plant. The results show about 10% difference between the reconstructed gamma radiation field data and the measured data which is sufficient for radiation protection studies of nuclear facilities and for optimizing radiation protection procedures.

关键词

辐射剂量学 / 点核积分 / 源活度反演 / γ辐射场

Key words

radiation dosimetry / point-kernel integration / source activity inversion / γ-radiation field

引用本文

导出引用
李华, 赵原, 曹勤剑, 何良, 李君利, 刘立业. 基于源活度反演计算的γ辐射场数据重构方法[J]. 清华大学学报(自然科学版). 2020, 60(10): 880-886 https://doi.org/10.16511/j.cnki.qhdxxb.2020.25.014
LI Hua, ZHAO Yuan, CAO Qinjian, HE Liang, LI Junli, LIU Liye. γ-radiation field reconstruction method basedon source activity inversion calculations[J]. Journal of Tsinghua University(Science and Technology). 2020, 60(10): 880-886 https://doi.org/10.16511/j.cnki.qhdxxb.2020.25.014

参考文献

[1] OHGA Y, FUKUDA M, SHIBATA K, et al. A system for the calculation and visualization of radiation field for maintenance support in nuclear power plants[J]. Radiation Protection Dosimetry, 2005, 116(1-4):592-596.
[2] MÓL A C A, PEREIRA C M N A, FREITAS V G G, et al. Radiation dose rate map interpolation in nuclear plants using neural networks and virtual reality techniques[J]. Annals of Nuclear Energy, 2011, 38(2-3):705-712.
[3] RÓDENAS J, ZARZA I, BURGOS M C, et al. Developing a virtual reality application for training nuclear power plant operators:Setting up a database containing dose rates in the refuelling plant[J]. Radiation Protection Dosimetry, 2004, 111(2):173-180.
[4] JEONG K S, CHOI B S, MOON J K, et al. Real-time assessment of exposure dose to workers in radiological environments during decommissioning of nuclear facilities[J]. Annals of Nuclear Energy, 2014, 73:441-445.
[5] DA SILVA M H, DO ESPÍRITO SANTO A C, MARINS E R, el al. Using virtual reality to support the physical security of nuclear facilities[J]. Progress in Nuclear Energy, 2015, 78:19-24.
[6] SAUNDERS P. Exposure reduction through optimized planning and scheduling:Guidance on incorporating ALARA concepts[R]. Palo Alto, USA:Electric Power Research Institute (EPRI), 2005.
[7] VERMEERSCH F. ALARA pre-job studies using the VISIPLAN 3D ALARA planning tool[J]. Radiation Protection Dosimetry, 2005, 115(1-4):294-297.
[8] VERMEERSCH F. VISIPLAN 4.03D ALARA planning tool user's manual[Z]. Antwerp, Belgium:SCK·CEN, 2006.
[9] SAUNDERS P, RAHON T, QUINN D, et al. Demonstration of advanced 3D ALARA planning prototypes for dose reduction[R]. Palo Alto, USA:EPRI, 2012.
[10] 李春槐. 点核积分程序研制和发展[J]. 核动力工程, 2001, 22(1):19-21, 41. LI C H. Development and improvement in point-kernel integral computer code[J]. Nuclear Power Engineering, 2001, 22(1):19-21, 41. (in Chinese)
[11] 李华, 赵原, 刘立业, 等. 基于MCNP对γ射线吸收剂量累积因子的计算与研究[J]. 辐射防护, 2017, 37(3):161-168. LI H, ZHAO Y, LIU L Y, et al. Research on gamma ray buildup factor for energy absorption based on MCNP[J]. Radiation Protection, 2017, 37(3):161-168. (in Chinese)
[12] 李华, 赵原, 刘立业, 等. 介质尺寸对水中γ射线吸收剂量累积因子的影响[J]. 清华大学学报(自然科学版), 2017, 57(5):525-529. LI H, ZHAO Y, LIU L Y, et al. Effect of medium size on the γ-ray buildup factor for energy absorption in water[J]. Journal of Tsinghua University (Science and Technology), 2017, 57(5):525-529. (in Chinese)
[13] 刘立业, 曹勤剑, 熊万春, 等. 基于高纯锗探测器的核电厂一回路系统辐射源项就地γ谱测量[J]. 辐射防护, 2015, 35(5):257-261. LIU L Y, CAO Q Q, XIONG W C, et al. In-situ gamma-spectrometry measurement of radiological source term for primary system of NPPs based on HPGe detector[J]. Radiation Protection, 2015, 35(5):257-261. (in Chinese)
[14] 刘立业, 马吉增, 张斌全, 等. Monte Carlo方法用于就地γ辐射源项调查与剂量评估[J]. 清华大学学报(自然科学版), 2007, 47(S1):991-995. LIU L Y, MA J Z, ZHANG B Q, et al. Monte Carlo method for in situ gamma radiological characterization and dose estimation[J]. Journal of Tsinghua University (Science and Technology), 2007, 47(S1):991-995. (in Chinese)

基金

刘立业,研究员,E-mail:liuliye@cirp.org.cn

PDF(2582 KB)

Accesses

Citation

Detail

段落导航
相关文章

/