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The Validation of Comprehensive Software for the Assessment of Radiological Impacts on Humans Through Benchmark Analysis with Radiological Codes.
Radiation Protection Dosimetry ( IF 0.8 ) Pub Date : 2020-07-29 , DOI: 10.1093/rpd/ncaa095
Ali Haghighi Shad 1 , Mitra Athari Allaf 1 , Darioush Masti 2 , Kamran Sepanloo 3 , Seyed Amir Hossein Feghhi 4
Affiliation  

In this paper, a novel domestic code called KIANA was developed for the assessment of radiological impacts on the population in normal and accident conditions including design basis accident (DBA) and beyond DBA (BDBA) for the nuclear power plants. The validation process of the KIANA code was performed using the results of the DOZA_M radiological code, whose results are presented in the Final Safety Analysis Report (FSAR) of the Bushehr Nuclear Power Plant Unit One (BNPP-1). The calculations of KIANA are performed based on the Gaussian diffusion model. The developed KIANA code has the potential of calculating the concentration and radionuclide doses due to the pathways such as airborne, foodstuff, marine (both one and two boxes models), soils, animals, vegetation (with and without tritium) and other pathways without any restriction. In the current research, the individual dose from a cloud to the member of the public in the region of BNPP-1 in normal condition was calculated. Moreover, the total effective dose to the member of the public from the primary to the secondary leakage inside steam generators, large break loss-of-coolant accident (LBLOCA) and small break loss-of-coolant accident was calculated. Thyroid gland equivalent dose for the infant (1–8 years) in the case of LBLOCA at the BNPP in DBA conditions was also evaluated. Finally, the prevented dose at the initial stage for the whole body of adults after BDBA, prevented dose at the initial stage for the thyroid gland of children after BDBA and the effective dose during the first year after the accident (external body irradiation from presence in the area) in the case of BDBA are assessed. The KIANA simulation results showed a good agreement with the FSAR data of BNPP.

中文翻译:

通过使用放射性法规进行基准分析,评估对人类的放射性影响的综合软件的验证。

在本文中,开发了一种名为KIANA的新颖的国内法规,用于评估核电厂在正常和事故条件下的辐射对人口的辐射影响,包括设计基准事故(DBA)和超出DBA(BDBA)的事故。KIANA代码的验证过程使用DOZA_M放射代码的结果执行,其结果显示在布什尔核电站一号机组(BNPP-1)的最终安全分析报告(FSAR)中。KIANA的计算是基于高斯扩散模型进行的。由于空气传播,食品,海洋(一箱和两箱模型),土壤,动物,植被(有或没有tri)等途径,因此发达的KIANA代码具有计算浓度和放射性核素剂量的潜力。限制。在当前的研究中,计算了正常情况下从云到BNPP-1区域公众的个人剂量。此外,计算了从蒸汽发生器内部一次泄漏到二次泄漏,大的冷却液损失事故(LBLOCA)和小的冷却液损失事故对公众的总有效剂量。还评估了在DBA条件下,在BNPP的LBLOCA情况下婴儿(1至8岁)的甲状腺等效剂量。最后,BDBA术后成人全身初始阶段的预防剂量,BDBA术后儿童甲状腺常规阶段的预防剂量以及事故发生后第一年的有效剂量(因存在于体外而受到的体外照射)区域)(如果是BDBA)。
更新日期:2020-09-16
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