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Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions

机译:正常运行和事故情况下布什尔核电站烟囱中放射性核素弥散的剂量评估

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Assessment of individual and collective doses around the unit-1 of Bushehr nuclear power plant (BNPP-1) site during normal nuclear reactor operation and under reactor accident conditions which are essential for safety and environmental analyses is presented in this paper. Release of radioactive materials to the environment following a design basic accident (DBA) (e.g. LBLOCA) is evaluated using HOTSPOT health physics computer code. In the normal operation conditions, atmospheric dispersion of radioactive material is calculated using CAP88-PC code. These codes utilize a Gaussian dispersion air transport plume model to simulate the atmospheric dispersion of radionuclides in different atmospheric stability classes and various wind speeds and directions. To calculate the doses under normal operation using CAP88 code, the surrounding area of the BNPP-1 within a radius of 30 km is gridded into 12 concentric rings and 16 sectors and the distribution of population and data of agricultural products are calculated for each grid. The meteorological data on atmospheric stability conditions, wind speed and the frequency distribution of wind direction based on data collected near the reactor site are also analyzed and applied. The results illustrate that the maximum total effective dose equivalent (TEDE) and committed effective dose equivalent (CEDE) values for personnel and public around the BNPP-1 site are lower than the annual effective dose limits for workers and public in normal operation and under accident conditions. Also, the results of the radiological impacts of the BNPP-1 in normal and accidental radioactive materials releases are compared with the dose values given in the Final Safety Analysis Report (FSAR) of the BNPP-1. Copyright (C) 2015, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved.
机译:本文介绍了在正常核反应堆运行期间以及在安全和环境分析必不可少的反应堆事故情况下,对布什尔核电站(BNPP-1)第1号机组附近的个人和集体剂量的评估。使用HOTSPOT健康物理学计算机代码评估设计基本事故(DBA)(例如LBLOCA)之后向环境释放的放射性物质。在正常运行条件下,放射性物质在大气中的扩散是使用CAP88-PC代码计算的。这些代码利用高斯扩散空气传播羽流模型来模拟不同大气稳定性等级以及不同风速和风向的放射性核素在大气中的扩散。为了使用CAP88代码在正常操作下计算剂量,将BNPP-1周围30公里半径内的区域划分为12个同心环和16个扇区,并为每个网格计算人口分布和农产品数据。还基于反应堆附近收集的数据分析了大气稳定条件,风速和风向频率分布的气象数据。结果表明,BNPP-1站点周围人员和公众的最大总有效剂量当量(TEDE)和承诺有效剂量当量(CEDE)值低于正常操作和意外情况下工人和公众的年度有效剂量限值条件。此外,将BNPP-1在正常和意外放射性物质释放中的放射学影响结果与BNPP-1的最终安全性分析报告(FSAR)中给出的剂量值进行了比较。 Hydrogen Energy Publications,LLC版权所有(C)2015。由Elsevier Ltd.出版。保留所有权利。

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