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Assessment of Radiation Dose Associated with the Atmospheric Release of 41Ar from the TRIGA Mark-II Research Reactor in Bangladesh 与孟加拉国 TRIGA Mark-II 研究反应堆向大气释放 41Ar 有关的辐射剂量评估
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-05-30 DOI: 10.1155/2024/9141535
M. Ajijul Hoq, M. A. Malek Soner, S. Khanom, M. J. Uddin, M. Moniruzzaman, M. S. H. Chowdhury, A. Helal, M. Abu Khaer, S. M. T. Hassan, M. Tareque Chowdhury, M. Mizanur Rahman
A major concern for nuclear research reactors under normal operating conditions is that they may release radioactive elements into the atmosphere, endangering public health and the environment. The present study concentrated on the detailed radiological dose assessment resulting from the atmospheric release of 41Ar activity from the TRIGA Mark-II research reactor in Bangladesh during its normal operational condition at full power of 3 MW. The total effective dose equivalent (TEDE), ground deposition activity, organ-committed dose, and pathways dose values have been evaluated under different weather conditions using the HotSpot 3.1.2 code. The weather data have been gathered from the Bangladesh Meteorological Department (BMD), Dhaka. Two significant seasons with various weather stability effects have been considered for dose analysis. Atmospheric dispersion of 41Ar was evaluated using the Gaussian plume model. From the obtained results, the maximum TEDE of 4.06 × 10−9 Sv at 0.19 km distance from the reactor site for stability class B during the summer season is found to be well below the annual effective dose limit of 1 mSv recommended by the ICRP. During the rainy season, the maximum TEDE of 1.76 × 10−9 Sv at 0.92 km distance for stability class E is also found to be negligible compared to the dose limit. From the organ-committed dose analysis, skin is investigated as the highest dose absorber compared to other organs. The pathways dose analysis concludes that the submersion and ground shine doses are observed to be maximum at 0.20 km and 1.0 km distances for the summer and rainy seasons, respectively. Based on the identified results, dose values have been found to be within the limiting values, ensuring environmental and human health safety. Such comprehensive dose analysis due to the atmospheric release of 41Ar activity is very significant from the perspective of ensuring the radiological and environmental safety of research-type nuclear reactors under normal operational conditions.
核研究反应堆在正常运行条件下的一个主要问题是,它们可能会向大气释放放射性元素,从而危及公众健康和环境。本研究主要对孟加拉国 TRIGA Mark-II 研究堆在 3 兆瓦全功率正常运行状态下向大气释放 41Ar 放射性活度所产生的辐射剂量进行了详细评估。利用 HotSpot 3.1.2 代码对不同天气条件下的总有效剂量当量(TEDE)、地面沉积活度、器官承诺剂量和路径剂量值进行了评估。气象数据来自达卡的孟加拉国气象局(BMD)。剂量分析考虑了两个具有不同天气稳定性影响的重要季节。使用高斯烟羽模型对 41Ar 的大气扩散进行了评估。从得到的结果来看,在夏季,稳定性等级为 B 级的反应堆场址 0.19 公里处的最大 TEDE 为 4.06 × 10-9 Sv,远低于国际放射防护委员会建议的 1 mSv 年有效剂量限值。在雨季,穩定度等級 E 距離 0.92 公里處的最大熱釋光劑量為 1.76 × 10-9 希沃特,與劑量限值相比也是微不足道。从器官承诺剂量分析来看,与其他器官相比,皮肤吸收的剂量最高。路径剂量分析得出的结论是,在夏季和雨季,浸没剂量和地面照射剂量分别在 0.20 千米和 1.0 千米处最大。根据确定的结果,发现剂量值在极限值范围内,确保了环境和人类健康安全。从确保研究型核反应堆在正常运行条件下的辐射安全和环境安全的角度来看,这种因大气释放 41Ar 活性而产生的综合剂量分析意义重大。
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引用次数: 0
Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning 核电站退役期间暖通空调系统的设计变更和运行考量
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-30 DOI: 10.1155/2024/4701409
Ho-Jin Jeon, Chang-Lak Kim
The heating, ventilation, and air conditioning (HVAC) system plays a crucial role in ensuring the safety of workers and preventing the release of gaseous radioactive materials into the environment during the decommissioning of a nuclear power plant (NPP). To establish an HVAC operation strategy, decommissioning phases were divided into four stages, and the HVAC systems were reclassified. In addition, assumptions have been made regarding design modifications and maintenance for the reactor containment building (RCB) HVAC, fuel handling building (FHB) HVAC, and main control room (MCR) HVAC. Based on these, for RCB HVAC operation, natural ventilation and RCB purge operation during the transition period are proposed. In the decommissioning stage, recirculation operation, entire ventilation operation consisting of continuous operation and purge operation, and finally partial ventilation operation to purify local space were proposed. Moreover, during the transition period, the FHB HVAC was proposed to operate as normal NPP, and the MCR HVAC was suggested to operate with safety-related equipment removed.
在核电站(NPP)退役期间,供暖、通风和空调系统(HVAC)在确保工人安全和防止气态放射性物质释放到环境中起着至关重要的作用。为制定暖通空调运行策略,退役阶段被分为四个阶段,暖通空调系统也被重新分类。此外,还对反应堆安全壳建筑 (RCB) 暖通空调系统、燃料处理建筑 (FHB) 暖通空调系统和主控室 (MCR) 暖通空调系统的设计修改和维护进行了假设。在此基础上,就反应堆安全壳大楼暖通空调系统的运行提出了过渡时期自然通风和反应堆安全壳大楼吹扫运行的建议。在退役阶段,提出了再循环运行、由连续运行和净化运行组成的整体通风运行,以及最后的局部通风运行,以净化局部空间。此外,在过渡时期,建议 FHB HVAC 按正常 NPP 运行,而 MCR HVAC 则在拆除安全相关设备后运行。
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引用次数: 0
Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B-VIII.0 and JENDL-5 Libraries for 10 MWth Micro Heat Pipe-Cooled Reactor 使用ENDF/B-VIII.0和JENDL-5库对10 MWth微型热管冷却反应堆的蒙特卡洛模拟结果进行精度评估
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-08 DOI: 10.1155/2024/5565346
Thanh Mai Vu, Le Quang Linh Tran
The micro heat pipe-cooled reactor is an innovative type of reactor that utilizes heat pipes to cool its core. It consists of a reactor core, an energy conversion system, shielding, and a heat removal system. This reactor shows great potential as a viable option for supplying electricity in remote areas. By incorporating a monolithic core with heat pipes and an efficient heat conversion system, this reactor design eliminates the need for a main pipeline, circulating pump, and auxiliary equipment, resulting in a cost-effective, compact, and transportable system. The monolithic reactor design has undergone significant advancements in neutronics and thermal hydraulics. This article focuses on evaluating the impact of the latest released nuclear data libraries, ENDF/B-VIII.0 and JENDL-5, on calculated neutronics and kinetics parameters. The total keff uncertainty was propagated and found to be significant for both recently evaluated nuclear data libraries (678.52 pcm for ENDF/B-VIII.0 and 525.91 pcm for JENDL-5, respectively). The total uncertainty originated from nuclear data was evaluated for total ν, reaction cross sections, and angular distributions in the case of JENDL-5, and for ENDF/B-VIII.0, uncertainty from angular distributions was not included because of the unavailability of its multigroup structure covariance matrices. The results reveal that the largest contributor for ENDF/B-VIII.0 is 235U total (409.18 pcm), while that for JENDL-5 is 56Fe capture cross section (361.93 pcm). For the kinetic parameter’s uncertainty, the impact on the total βeff, leff, and λeff simulation results was found to be not significant (about 1%).
微型热管冷却反应堆是一种利用热管冷却堆芯的创新型反应堆。它由反应堆堆芯、能量转换系统、屏蔽和散热系统组成。作为向偏远地区供电的可行选择,这种反应堆显示出巨大的潜力。通过将带有热管和高效热转换系统的单片堆芯结合在一起,这种反应堆设计无需主管道、循环泵和辅助设备,从而形成了一个成本效益高、结构紧凑且便于运输的系统。整体式反应堆设计在中子学和热工水力学方面取得了重大进展。本文重点评估了最新发布的核数据库(ENDF/B-VIII.0 和 JENDL-5)对中子和动力学参数计算的影响。对这两个最新评估的核数据 库进行了 keff 总不确定性传播,发现其不确定性都很大(ENDF/B-VIII.0 和 JENDL-5 分别为 678.52 pcm 和 525.91 pcm)。对 JENDL-5 的总 ν、反应截面和角度分布进行了评估,而对于 ENDF/B-VIII.0,由于无法获得其多组结构协方差矩阵,因此不包括角度分布的不确定性。结果表明,ENDF/B-VIII.0 的最大不确定因素是 235U 的总量(409.18 pcm),而 JENDL-5 的最大不确定因素是 56Fe 的俘获截面(361.93 pcm)。对于动力学参数的不确定性,发现其对总 βeff、leff 和 λeff 模拟结果的影响并不显著(约 1%)。
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引用次数: 0
Effect of Photomultiplier Tube Voltage on the Performance of Sealed NaI (Tl) Scintillator Detectors 光电倍增管电压对密封式 NaI (Tl) 闪烁探测器性能的影响
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-03 DOI: 10.1155/2024/5206668
Hongchi Zhou, Fang Liu, Xin Yuan, Jun Wu, Guanda Li
We explored the nonlinear characteristics of energy resolution (ER) for the sealed NaI (Tl) scintillator detector by using a gamma-ray spectroscopy system and Monte Carlo simulation. Our research focused on the two primary factors of energy resolution including the photomultiplier tube (PMT) voltage and the distance between the gamma-ray sources (137Cs and 60Co) and the scintillator detector. The experimental results showed that energy resolution decreased when the PMT voltage increased, and the energy resolution of NaI (Tl) detectors reached a smaller value (6.92%, 6.76%, and 6.56%), especially with the PMT voltage in the range of 575–595 V. In addition, a suitable distance between the gamma-ray source and the scintillator (5 cm) can also effectively reduce the energy resolution. We established the simulation models of the experimental NaI (Tl) detectors and simulated their energy spectra. The simulation results in the peak area agreed with the experimental results. A possible better PMT voltage choice has been proposed to obtain a smaller energy resolution.
我们利用伽马射线光谱系统和蒙特卡洛模拟,探索了密封式碘化钛(NaI (Tl))闪烁体探测器能量分辨率(ER)的非线性特性。我们的研究重点是能量分辨率的两个主要因素,包括光电倍增管(PMT)电压和伽马射线源(137Cs 和 60Co)与闪烁探测器之间的距离。实验结果表明,当光电倍增管电压升高时,能量分辨率降低,NaI(Tl)探测器的能量分辨率达到了较小值(6.92%、6.76%和6.56%),尤其是当光电倍增管电压在575-595 V范围内时。此外,伽马射线源与闪烁体之间的适当距离(5 厘米)也能有效降低能量分辨率。我们建立了实验用 NaI (Tl) 探测器的模拟模型,并模拟了它们的能谱。峰面积的模拟结果与实验结果一致。为了获得更小的能量分辨率,我们提出了一个更好的 PMT 电压选择方案。
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引用次数: 0
An Association Rule Mining-Based Method for Revealing the Impact of Operational Sequence on Nuclear Power Plants Operating 基于关联规则挖掘的方法揭示运行顺序对核电站运行的影响
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-25 DOI: 10.1155/2024/6618975
Yuxuan He, Jian Song, Shaoke Shi, Haibo Lian, Jiangyang He, Ren Yu, Tete Liu, Bin Sun, Jiangtao Yuan, Yingbin Hu
The operations of the operators are important for nuclear safety, but conventional operating experience feedback and common data-driven methods make it difficult to explicitly find valuable information hidden in these operational sequences that can help the operator to provide advice at the operational level. During the nuclear power plant (NPP) operation, a large amount of historical operating data is accumulated, which records the operational sequences of the operators and the state parameters of equipment. Therefore, this paper proposes the use of association rule techniques to mine the NPP operating data to discover the operational characteristics of operators and reveal their possible impact on the NPP operation. This work helps to improve the operational performance of operators and prevent human-factor events. To this end, the concept of state switching values for describing the operating states of NPPs is proposed to enable the proposed method to be adapted to different practical application scenarios. A sequence segmentation method is proposed to be able to transform historical NPP operating data into a sequence data set for association rule mining. Furthermore, an ensemble algorithm based on sequence pattern mining and sequence rule mining and its postprocessing method are designed. The empirical study was carried out using 20 batches of historical operating data of the cold start-up. A total of 164 original association rules are generated using the proposed method and were analyzed by experts. The recommendations were made for 4 different cases that would improve the operational performance of the operators.
操作人员的操作对核安全非常重要,但传统的操作经验反馈和常见的数据驱动方法很难明确找到隐藏在这些操作序列中的有价值信息,从而帮助操作人员在操作层面提供建议。在核电站(NPP)运行过程中,积累了大量的历史运行数据,这些数据记录了操作人员的操作序列和设备的状态参数。因此,本文提出利用关联规则技术挖掘核电站运行数据,以发现操作人员的操作特征,并揭示其对核电站运行可能产生的影响。这项工作有助于提高操作员的操作绩效,防止人为因素事件的发生。为此,提出了用于描述核电站运行状态的状态切换值概念,使所提出的方法能够适应不同的实际应用场景。提出了一种序列分割方法,以便能够将核电厂的历史运行数据转化为序列数据集,用于关联规则挖掘。此外,还设计了一种基于序列模式挖掘和序列规则挖掘的集合算法及其后处理方法。实证研究使用了 20 批冷启动历史运行数据。使用所提出的方法共生成了 164 条原始关联规则,并由专家进行了分析。针对 4 种不同情况提出了建议,以提高操作员的操作性能。
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引用次数: 0
Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo-Kopalino and Pątnów Sites in Poland 常规运行期间气体排放的定量评估:波兰 Lubiatowo-Kopalino 和 Pątnów 核电站规划比较研究
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-12 DOI: 10.1155/2024/8699926
Edyta Agata Macieja, Juyoul Kim
On September 2021, Polish government declared that six pressurized water reactors with combined capacity of 6–9 GWe will be built by 2040 to reduce Poland’s reliance on coal. Due to the adopted schedule, construction of the first nuclear power plant will begin in 2026, with the first reactor capacity of 1–1.6 GWe to be operational in 2033. The Polish authorities announced in 2022 the selection of two locations and technologies for Poland’s first commercial nuclear power plants. Westinghouse AP1000 reactor was selected by Polish government to be built as the first plant in the location of Lubiatowo-Kopalino, on the coast of the country. In the meantime, Poland’s ZE PAK, Polska Grupa Energetyczna, and Korea Hydro & Nuclear Power have signed the letter of intent to collaborate on the project that evaluates the feasibility of building South Korean APR1400 on Pątnów site in central Poland. The objective of this study was to acquire and examine the gaseous effluents released during the standard operation of the AP1000 and APR1400 reactor technologies, with the primary goal of focusing on estimating the potential exposure of the general public. The effluents were calculated by using the GALE code based on each nuclear reactor technical specification. The obtained results were compared with those included in the Design Control Document for each reactor. Subsequently, the HotSpot software was used to calculate the radiation risk for downwind areas by utilizing GALE code results as source terms together with specific meteorological data corresponding for each localization. The results for AP1000 at Lubiatowo-Kopalino site and for APR1400 at Pątnów site were analysed and compared in the study. As the study findings were evaluated with the Polish radiation limits for the general public, all doses remained below the legal thresholds. With no previous alike studies conducted, this research begins the analysis of radiation impacts associated with the planned nuclear power plant in Poland during normal operation.
2021 年 9 月,波兰政府宣布将在 2040 年之前建造 6 座总容量为 6-9 GWe 的压水反应堆,以减少波兰对煤炭的依赖。根据已通过的时间表,第一座核电站将于 2026 年开工建设,首座反应堆的发电能力为 1-1.6 GWe,将于 2033 年投入运行。波兰当局于 2022 年宣布了波兰首座商业核电站的两个选址和技术。西屋 AP1000 反应堆被波兰政府选中,将作为第一座核电站建在该国沿海的 Lubiatowo-Kopalino 地区。与此同时,波兰 ZE PAK 公司、波兰能源集团(Polska Grupa Energetyczna)和韩国水电与核电公司(Korea Hydro & Nuclear Power)签署了项目合作意向书,对在波兰中部 Pątnów 建造韩国 APR1400 核电站的可行性进行评估。这项研究的目的是获取并检查 AP1000 和 APR1400 反应堆技术在标准运行期间释放的气体流出物,主要目标是估算公众可能受到的辐射。根据每个核反应堆的技术规格,使用 GALE 代码计算流出物。获得的结果与每个反应堆的设计控制文件中的结果进行了比较。随后,使用 HotSpot 软件计算下风向地区的辐射风险,将 GALE 代码结果作为源项,并结合与每个地方相应的具体气象数据。研究分析并比较了 Lubiatowo-Kopalino 现场的 AP1000 和 Pątnów 现场的 APR1400 的结果。由于研究结果是根据波兰公众辐射限值进行评估的,因此所有剂量都低于法定阈值。由于之前没有进行过类似的研究,这项研究开始分析波兰计划中的核电站在正常运行期间的辐射影响。
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引用次数: 0
Time-Series Forecasting of a Typical PWR Undergoing Large Break LOCA 对发生大断裂 LOCA 的典型压水堆进行时序预测
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-08 DOI: 10.1155/2024/6162232
Michal Kaminski, Aya Diab
In this work, a machine learning (ML) metamodel is developed for the time-series forecasting of a typical nuclear power plant response undergoing a loss of coolant accident (LOCA). The plant model of choice is based on the APR1400 nuclear reactor. The key systems and components of APR1400 relevant to the investigated scenario are modelled using the thermal-hydraulic code, RELAP5/MOD3.4, following the description published in the design control document. The model is tested under a spectrum of initial and boundary conditions via propagation of key uncertain parameters (UPs) which are derived from the phenomena identification and ranking table (PIRT). This is achieved by loosely coupling RELAP5/MOD3.4 with the statistical tool, Dakota. The most probable nuclear power plant (NPP) response was calculated using the best estimate plus uncertainty (BEPU) approach. Next, the database generated from the NPP system response was used as an input for the ML model. The NPP system response was represented by peak cladding temperature (PCT), safety injection system (SIT), mass flow rate, reactor power, and primary system pressure. In this research, two regression models were tested with reasonably good performance, namely, the gated recurrent unit (GRU) and the long short-term memory (LSTM).
在这项工作中,开发了一种机器学习(ML)元模型,用于对发生冷却剂损失事故(LOCA)的典型核电厂响应进行时间序列预测。选择的核电厂模型基于 APR1400 核反应堆。APR1400 核反应堆的关键系统和组件与调查情景相关,按照设计控制文件中公布的说明,使用 RELAP5/MOD3.4 热液压代码进行建模。通过传播从现象识别和排序表(PIRT)中导出的关键不确定参数(UPs),在一系列初始和边界条件下对模型进行测试。这是通过将 RELAP5/MOD3.4 与统计工具 Dakota 松耦合实现的。使用最佳估计加不确定性(BEPU)方法计算出最可能的核电厂(NPP)响应。接下来,从核电厂系统响应生成的数据库被用作 ML 模型的输入。国家核电厂系统响应由包壳峰值温度 (PCT)、安全注入系统 (SIT)、质量流量、反应堆功率和一次系统压力表示。在这项研究中,测试了两种性能相当不错的回归模型,即门控递归单元(GRU)和长短期记忆(LSTM)。
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引用次数: 0
Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site 在达巴核电厂通过核应急准备提高复原力
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-13 DOI: 10.1155/2024/9345812
Waad Saleh, Juyoul Kim
The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss-of-coolant accident (LOCA) and long-term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the dispersion of radioactive substances within a 40-kilometer radius across all four seasons. The outcomes revealed that only in the case of LTSBO did the radiological levels surpass the limits set by the Environmental Protection Agency (EPA). Notably, during spring, LTSBO exhibited a maximum total effective dose equivalent (TEDE) value of 13 millisieverts (mSv) at a distance of 3.2 kilometers, and the highest thyroid dose (TD) recorded was 63 mSv at 8 kilometers. These significant findings play a crucial role in shaping strategies related to the distribution of potassium iodide (KI) and further enhance the overall preparedness and evacuation planning protocols.
这项研究利用先进的 PCTRAN 和 RASCAL 软件来评估假设事故(特别是达巴核电站的失冷事故和长期停电事故)可能造成的辐射影响。对十年间的综合气象数据进行了细致分析,以评估放射性物质在方圆 40 公里范围内一年四季的扩散情况。结果显示,只有在 LTSBO 的情况下,放射性水平才超过了环境保护局(EPA)规定的限值。值得注意的是,在春季,LTSBO 在 3.2 公里处的最大总有效剂量当量 (TEDE) 值为 13 毫西弗 (mSv),在 8 公里处记录到的最高甲状腺剂量 (TD) 为 63 毫西弗。这些重要发现对制定与碘化钾(KI)分配相关的战略起到了关键作用,并进一步加强了整体备灾和疏散规划协议。
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引用次数: 0
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process 科里 1 号机组蒸汽发生器拆除过程中工人辐射暴露评估
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-01-30 DOI: 10.1155/2024/4230293
Hyeon-Ki Kim, Sang-Hwa Shin, Chang-Sig Kong, Chang-Lak Kim
Kori Unit 1 was permanently shut down on June 18, 2017. Since then, Korea is actively preparing for the decommissioning of the nuclear power plant. Because decommissioning work is performed in a radioactive environment, worker radiation exposure is a significant consideration. In this study, worker radiation exposure is evaluated during the steam generator, one of the heavy components of nuclear power plant, dismantling process. A radiation evaluation for the dismantling process is performed using the code RESRAD-BUILD. A steam generator dismantling scenario and optimal cutting method are designed to evaluate worker radiation exposure, considering pipe dimensions, cutting tool speed, and experience in steam generator replacement. The evaluation results are derived for each work type and year. As a result of the evaluation, worker radiation exposure is 7.5 man-mSv at the year of planned decommissioning.
科里 1 号机组于 2017 年 6 月 18 日永久关闭。从那时起,韩国就开始积极准备核电站的退役工作。由于退役工作是在放射性环境中进行的,因此工人的辐射暴露是一个重要的考虑因素。在本研究中,对核电站重型部件之一的蒸汽发生器拆除过程中的工人辐射照射进行了评估。使用 RESRAD-BUILD 代码对拆除过程进行了辐射评估。考虑到管道尺寸、切割工具速度和蒸汽发生器更换经验,设计了蒸汽发生器拆除方案和最佳切割方法,以评估工人受到的辐射。评估结果针对每个工种和年份得出。评估结果表明,在计划退役的年份,工人受到的辐射量为 7.5 man-mSv。
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引用次数: 0
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model 利用亚当优化 BP 神经网络模型检测运输过程中未经授权的放射性物质包裹移动情况
IF 1.1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2023-12-18 DOI: 10.1155/2023/6363270
Panpan Jiang, Xiaohua Yang, Yaping Wan, Tiejun Zeng, Mingxing Nie, Chaofeng Wang, Yu Mao, Zhenghai Liu
The rapid expansion of nuclear technology across various sectors due to global economic growth has led to a substantial rise in the transportation of radioactive materials. The International Atomic Energy Agency (IAEA) estimates that approximately 20 million shipments of radioactive materials occur annually. In this context, ensuring the safety and security of radioactive material transportation is of significant importance. IAEA’s “Security of Radioactive Materials in Transport” (Nuclear Security Series No. 9-G) mandates that an effective transport security system should provide immediate detection of any unauthorized removal of the packages. In the present study, an innovative Adam-optimized BP neural network model is developed for detecting unauthorized movements of radioactive material packages. To analyze the performance of the proposed algorithm, numerous experiments were conducted. The results demonstrate that the proposed method achieves a 99.17% accuracy rate in detecting unauthorized movements of radioactive materials, with a missed alarm rate of 0.72% and a false alarm rate of 0.1%. This method also enables real-time detection of unauthorized removal of radioactive materials and effectively enhances the security of radioactive materials during transport to reduce the risks of theft, loss, diversion, or sabotage.
由于全球经济增长,核技术在各个领域迅速扩展,导致放射性材料的运输量大幅上升。据国际原子能机构(IAEA)估计,每年约有 2000 万次放射性材料运输。在这种情况下,确保放射性材料运输的安全和安保就显得尤为重要。国际原子能机构的 "放射性材料运输安全"(《核安全丛书》第 9-G 号)规定,有效的运输安全系统应能立即检测到任何未经授权的包裹移动。在本研究中,开发了一个创新的亚当优化 BP 神经网络模型,用于检测放射性物质包裹的未经授权移动。为分析所提算法的性能,进行了大量实验。结果表明,所提出的方法在检测未经授权的放射性物质移动方面达到了 99.17% 的准确率,漏报率为 0.72%,误报率为 0.1%。该方法还能实时检测未经授权移动放射性物质的情况,有效提高放射性物质在运输过程中的安全性,降低被盗、丢失、转移或破坏的风险。
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Science and Technology of Nuclear Installations
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