巴拉卡核电站综合剂量测定分析:综合多个机组的气体和液体放射性核素扩散情况

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2024-07-19 DOI:10.1016/j.pnucene.2024.105357
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引用次数: 0

摘要

监测发电厂正常运行期间的放射性释放对确保符合环境安全监管机构设定的安全限值至关重要。在阿联酋巴拉卡核电站的案例中,我们进行了全面的多单元扩散建模和辐射安全分析。利用 HotSpot 健康物理学代码和 GENII(第二代环境剂量学),对 GALE 生成的 37 个气态和 51 个液态源项进行了评估。源项的释放率是根据 APR 1400 规格使用 GALE 确定的。HotSpot 采用高斯烟羽模型模拟气态源项在工厂周围 80 公里范围内的扩散情况,计算农村和城市地区的总有效剂量当量 (TEDE) 和承诺有效剂量当量 (CEDE)。研究结果表明,这两种情况对一般公众而言都没有超过 1 mSv 的阈值,对操作工人而言也没有超过 20 mSv 的限制。值得注意的是,皮肤、甲状腺和骨骼表面的 CEDE 值最高,主要受碘放射性核素的影响。GENII 的地表水模块模拟了液体源项的影响,考虑了各种污染和照射途径,如不同年龄组的外部照射和摄入。计算得出的剂量仍远低于 FANR 的年度限值,预测一年辐照的癌症发病率和死亡人数均可忽略不计。
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A comprehensive dosimetry analysis of barakah nuclear power plant: Integrating gaseous and liquid radionuclide dispersion across multiple units

Monitoring radioactive releases during the normal operation of power plants is crucial to ensure compliance with safety limits set by regulatory bodies for environmental safety. In the case of the Barakah nuclear power plant in the UAE, comprehensive multiunit dispersion modelling and radiological safety analysis have been conducted. Utilizing the HotSpot Health Physics Code and GENII (Second-generation environmental dosimetry), assessments were made for both 37 gaseous and 51 liquid source terms generated by GALE. Release rates for source terms were determined using GALE based on APR 1400 specifications. HotSpot employed the Gaussian Plume model to simulate the dispersion of gaseous source terms up to 80 km surrounding the plant, calculating Total Effective Dose Equivalent (TEDE) and Committed Effective Dose Equivalent (CEDE) in rural and urban areas. Findings indicated that neither scenario exceeded the 1 mSv threshold for the general public nor the 20 mSv limit for operational workers. Notably, skin, thyroid, and surface bones exhibited the highest CEDE, primarily influenced by iodide radionuclides. GENII's Surface Water module modelled the effects of liquid source terms, accounting for various contamination and exposure pathways such as external exposure and ingestion across different age groups. The calculated doses remained well below FANR's annual limits, with negligible cancer incidences and fatalities predicted for one year of exposure.

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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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