Study on Fast Calculation of High-accuracy Radiation Field Based on Response Matrix Method
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摘要: 为解决传统输运计算方法无法兼顾快速性和精确性的不足,实现辐射防护最优化和屏蔽优化设计的快速迭代,开展了基于响应矩阵的高精度辐射场快速计算方法研究。研究采用基于响应矩阵的生物屏蔽深穿透快速计算方法和基于SOURCE源抽样的面源接续计算方法,将生物屏蔽入射源到生物屏蔽外空间辐射场计算过程拆分为生物屏蔽结构内的粒子输运计算和生物屏蔽外空间的粒子输运计算过程,实现反应堆装置复杂动态场景下的快速高精度剂量辐射场分析,计算效率相比蒙特卡罗(MC)直算方法提高100倍。本研究成果可为复杂辐照条件下人员辐射剂量最优化设计和屏蔽结构优化迭代提供有效、可靠的设计方法和工具。Abstract: To solve the problem that traditional transport calculation methods cannot take into account both rapidity and accuracy, and to realize the rapid iteration of radiation protection optimization and shielding optimization design, a fast calculation method of high-accuracy radiation field based on response matrix is developed. The biological shielding deep penetration fast calculation method based on response matrix and the surface source continuous calculation method based on SOURCE sampling technique are adopted. The calculation process of radiation field from the incident source of the biological shield to the outer space of the biological shield is divided into the calculation process of particle transport in the biological shield structure and the calculation process of particle transport in the outer space of the biological shield, so as to realize the rapid and high-precision dose radiation field analysis in the complex dynamic scene of the reactor unit. The calculation efficiency is 100 times higher than that of Monte Carlo (MC) direct calculation method. The results of this study can provide effective and reliable design methods and tools for personnel radiation dose optimization design and shielding structure optimization iteration under complex irradiation conditions.
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Key words:
- Biological shield /
- Radiation field /
- Response matrix method /
- Fast calculation
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表 1 不同方法总计算耗时
Table 1. Total Time-Consuming of Different Methods
不同辐射场计算方法 单核总计算耗时/min MC直算方法 辐射场快速计算 中子源入射 生物屏蔽输运计算耗时 2.24×105 7 生物屏蔽外接续计算耗时 2.50×103 光子源入射 生物屏蔽输运计算耗时 6.40×104 7 生物屏蔽外接续计算耗时 8.10×102 -
[1] CHALHOUB E S. Discrete-ordinates solution for radiative-transfer problems[J]. Journal of Quantitative Spectroscopy and Radiative Transfer, 2003, 76(2): 193-206. doi: 10.1016/S0022-4073(02)00053-5 [2] 尹增谦,管景峰,张晓宏,等. 蒙特卡罗方法及应用[J]. 物理与工程,2002, 12(3): 45-49. [3] 李春槐. 反应堆主回路设备间辐射屏蔽设计方法述评[J]. 核动力工程,2003, 24(5): 486-489. [4] 张磊,贾铭椿,龚军军,等. 反应堆辐射屏蔽计算方法与程序概述[J]. 核电子学与探测技术,2018, 38(4): 516-520. [5] 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. [6] VERMEERSCH F. ALARA pre-job studies using the VISIPLAN 3D ALARA planning tool[J]. Radiation Protection Dosimetry, 2005, 115(1-4): 294-297. doi: 10.1093/rpd/nci115 [7] THEVENON J B, TIREL O, LOPEZ L, et al. CHAVIR: virtual reality simulation for interventions in nuclear installations[C]//ANS NPIC&HMIT 2006 Albuquerque. La Grange Park: American Nuclear Society, 2006. [8] 宋英明,梁烨,叶凯萱,等. 核设施退役过程中的辐射场重构与拆除路径优化[J]. 核技术,2017, 40(5): 050502. [9] HE S X, ZANG Q Y, ZHANG J Y, et al. Development and validation of an interactive efficient dose rates distribution calculation program arshield for visualization of radiation field in nuclear power plant[J]. Radiation Protection Dosimetry, 2017, 174(2): 159-166. [10] BLANCHARD A. BUGLE-96 validation with MORSE-SGC/S using water and iron experiments from SINBAD 97: WSRC-TR-99-00349[R]. Aiken: Savannah River Site, 1999.