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密闭空间下放射性核素扩散研究及自主程序开发

Research on Radionuclide Diffusion in Confined Spaces and Development of Autonomous Code
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摘要 为了评估安全壳完整时发生一回路破口事故后,放射性核素在封闭空间中扩散时的个人受照剂量,对放射性核素扩散迁移过程开展模拟计算。采用隔室模型对密闭空间进行物理建模,使用多参数一阶动力学微分方程描述放射性核素在密闭空间内的迁移过程,自主开发了放射性核素扩散计算程序DMRC(Diffusion and Migration of Radi-onuclide Code)。采用DMRC程序计算了TACT(Transport of ACTivity)基准题中的放射性核素活度和假想个人剂量,计算结果与基准解结果符合良好。最后,对某真实核电厂一回路破口事故进行模拟,计算了事故发生后30天内安全壳和外部环境的放射性活度以及假想个人剂量。结果显示:该事故发生后公众接受的最大有效剂量及最大甲状腺当量剂量均小于国家规定限值。结果表明:本文工作可以用于事故工况下的环境安全分析和人员健康评估。 To assess the personal exposure dose during the diffusion of radionuclides in the confined space after a primary circuit break accident in an intact containment,the diffusion and migration process of radionuclides were simulated.First,the physics-based modeling of a con-fined space was carried out by the compartmental model.Subsequently,the migration process of radionuclide within the confined space was described by the multi-parameter first-order dynamic differential equation.Thereby,an independent code,the diffusion and migration of radionuclide code(DMRC),was developed to calculate the activity and hypothetical individual dose of radio-nuclide in TACT(Transport of ACTivity).Results obtained by DMRC was in accordance with the benchmark solution.Finally,a primary circuit break accident happened in a real nuclear power plant was simulated.The activity and the hypothetical personal dose of the ardionuclide within the containment and diffused in external environment 30 days after the accident were calculated re-spectively.Results showed that the maximum effective dose and maximum thyroid-equivalent dose received by the public after the accident are below the national limits.These demonstrated that the proposed method can be applied into environmental safety analysis and personnel health assessment during accident conditions.
作者 李昂 汪镇澜 郝琛 董峙豪 LI Ang;WANG Zhenan;HAO Chen;DONG Zhihao(Fundamental Science on Nuclear Safety and Simulation Technology Laboratory,Harbin Engineering University,Harbin 150001,Heilongjiang)
出处 《火箭军工程大学学报》 2024年第1期1-11,共11页 Journal of Rocket Force University of Engineering
关键词 破口事故 放射性核素扩散迁移 DMRC 假想个人剂量 break accident diffusion and migration of radionuclides DMRC hypothetical personal dose
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  • 1黄燕.海洋小型压水堆核事故核素扩散模型研究[J].产业与科技论坛,2021,20(8):48-50. 被引量:1
  • 2Accident source terms for light-water nuclear power plants, final report, NUREG-1465[R]. US: Nuclear Regulatory Commission, 1995. 被引量:1
  • 3MELCOR computer code manuals, Volume 1: RadioNuclide (RN) package users' guide[R]. USA.. Sandia National Laboratories, 2000. 被引量:1
  • 4Simulation of LBLOCA at the surry nuclear pow- er station (With no emergency core cooling sys- tem (ECCS) recovery), Vol. 3, NUREG. CR- 6119[R]. USA Sandia National Laboratories, 2001. 被引量:1
  • 5[J/T317-1998压水堆核电厂辐射屏蔽设计准则. 被引量:1
  • 6ORIGEN2程序使用说明,黄学清,等,中国核动力研究设计院,1987. 被引量:1
  • 7U. S. NRC Regulatory Guide 1. 183, " Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Reactors," July 2000. 被引量:1
  • 8Sorer, L, et al, "Accident Source Terms for Light- Water Nuclear Power Plants," NUGEF-1465, February 1995. 被引量:1
  • 9Powers D_A. , and Burson,S. B. , llA Simplified Model of Aerosol Removal byContainment Sprays," NUREG/ CR-5966, June 1993. 被引量:1
  • 10Petti, D.A. , Hobbins, R. R" and Hagrman, D. L. , The Composition of Aerosols Generated during a Severe Reactor Accident~ Experimental Results from the Power Burst Facility Severe Fuel Damage Test 1-4," Nucl. Tech. 105,p. 334 (1994). 被引量:1

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