Nuclear Engineering and Technology最新文献_第10页

Estimation of self-absorption correction factors for gamma-ray spectrometry of radioactive waste using MCNP 用MCNP估计放射性废物伽马射线能谱法的自吸收校正因子

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-12-01 DOI: 10.1016/j.net.2025.104064

Kyungmin Kim , Kyunghun Jung , Won-Hyuk Jang , Yu-Jeong Choi , Jong Soo Nam , Tack-Jin Kim , Gyuseong Cho

Gamma-ray spectrometry is a suitable technique for the radiological characterization of radioactive waste. However, differences in material and density between certified reference materials (CRMs) serve as standards for calibration. The waste sample can cause self-absorption effects, necessitating appropriate corrections. This study presents a practical method for deriving self-absorption correction factors using MCNP6.2. A detailed detector model and measurement setup were constructed in MCNP6.2 and optimized by comparing simulation results with experimental measurements. Three different CRM geometries were employed to improve modeling accuracy. Simulations were refined across three HPGe detectors within 59.54–1836.05 keV energy range to achieve average and maximum deviation between simulated and measured FEPE (full energy peak efficiency) of 1.9 ± 2.16 % and 4.9 ± 1.9 %, respectively. Using the optimized MCNP inputs, self-absorption correction factors were calculated with densities ranging from 0.1 to 8.0 g/cm³. Additionally, the corresponding equations for effective path lengths were determined for specific geometries. The self-absorption effects were further evaluated for combustible, incombustible, and metallic waste over the same density range. The correction factors were derived and compared by material type. The validity of the proposed method was experimentally confirmed using concrete-based CRM. The results will improve accuracy and efficiency in sampling and activity concentration analysis in radioactive waste management.

伽玛射线能谱法是一种适用于放射性废物的放射学表征的技术。然而，经认证的标准物质（crm）之间的物质和密度差异可作为校准标准。废样品会引起自吸收效应，需要适当的校正。本文提出了一种实用的利用MCNP6.2计算自吸收校正因子的方法。在MCNP6.2中建立了详细的探测器模型和测量装置，并通过对比仿真结果和实验结果对其进行了优化。采用三种不同的CRM几何形状来提高建模精度。在59.54-1836.05 keV的能量范围内，对三个HPGe探测器的模拟进行了细化，模拟和测量的FEPE（全能量峰值效率）的平均和最大偏差分别为1.9±2.16%和4.9±1.9%。利用优化后的MCNP输入，计算密度在0.1 ~ 8.0 g/cm3范围内的自吸收校正因子。此外，针对特定几何形状确定了相应的有效路径长度方程。在相同密度范围内，进一步评价了可燃、不燃和金属废物的自吸收效果。推导了修正系数，并按材料类型进行了比较。通过基于混凝土的CRM实验验证了该方法的有效性。研究结果将提高放射性废物管理中采样和活性浓度分析的准确性和效率。

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引用次数: 0

Redox-controlled sorption behavior of Re(VII) on bulk solid and colloidal bentonite 稀土（VII）在大块固体和胶体膨润土上的氧化还原控制吸附行为

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-12-25 DOI: 10.1016/j.net.2025.104102

Junhyuk Ha , Sang-Ho Lee , Jun-Yeop Lee

This study investigates the sorption behavior of Re(VII) onto bulk solid and colloidal phases of Bentonil-WRK bentonite under various reducing conditions. Reducing systems were established with Na₂S₂O₄, disodium anthraquinone-2,6-disulfonate, and DB-3 groundwater from the KAERI Underground Research Tunnel (KURT). Batch sorption experiments were conducted for 2500 h with an initial Re(VII) concentration of 10^−6.5 M and a solid-to-liquid ratio of 0.5 g/L. Measured pH and E_h values indicated the reduction of Re(VII) to Re(IV), consistent with thermodynamic predictions and confirmed by X-ray photoelectron spectroscopy. Sorption efficiency increased markedly after 500 h, highlighting the governing role of Re redox chemistry in such conditions. Faster sorption occurred in the DB-3 system, where Fe(II) ions and sulfur-bearing colloids enhanced Re retention. Sorption kinetic analysis indicated a redox-controlled sorption behavior of Re(VII) onto bulk solid and colloidal bentonite under the investigated reducing conditions. The results are expected to support more reliable predictions of the migration and retardation of redox-sensitive anionic radionuclides (e.g., Tc, for which Re serves as a chemical surrogate) in the reducing subsurface environment.

研究了不同还原条件下，Re（VII）在膨润土- wrk膨润土固体相和胶体相上的吸附行为。利用KAERI地下研究隧道（KURT）的Na2S2O4、蒽醌-2,6-二磺酸二钠和DB-3地下水建立了还原体系。间歇式吸附实验2500 h，初始Re（VII）浓度为10 ~ 6.5 M，料液比为0.5 g/L。测量的pH和Eh值表明Re（VII）还原为Re(IV)，与热力学预测一致，并经x射线光电子能谱证实。500h后吸附效率显著提高，表明在此条件下稀土氧化还原化学的调控作用。DB-3体系的吸附速度更快，其中Fe（II）离子和含硫胶体增强了Re的保留。吸附动力学分析表明，在所研究的还原条件下，稀土（VII）在大块固体和胶体膨润土上具有氧化还原控制的吸附行为。这些结果有望支持更可靠的预测氧化还原敏感阴离子放射性核素（例如，稀土作为化学替代物的Tc）在还原性地下环境中的迁移和阻滞。

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引用次数: 0

Influence of specimen size on the small strain dynamic properties and strength of compacted Bentonil-WRK bentonite for nuclear waste repository 核废料库用膨润土- wrk压实试样尺寸对其小应变动态特性及强度的影响

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-11-28 DOI: 10.1016/j.net.2025.104052

Jebie Balagosa , Ivan Jeff Navea , Minhyeong Lee , Seok Yoon , Yun Wook Choo

This study examines the small-strain dynamic properties and strength of highly compacted Bentonil-WRK bentonite, a candidate buffer material for engineered barrier system (EBS) in South Korea. Free-free resonant column (FFRC) and unconfined compressive tests (UCT) were performed on specimens with varying diameter sizes (Ø), dry density (ρ_d), and degree of saturation (S_r). FFRC determined shear, unconstrained and constrained compressive wave velocities (V_s, V_c, and V_p, respectively), small-strain moduli, material damping in shear (D_smin) and longitudinal (D_ucmin). The influence of increasing Ø, ρ_d, and S_r were investigated by utilizing seismic waves to (1) determine the dynamic stiffness, (2) characterize material damping, (3) permit direct calculation of dynamic Poisson's ratio (v), and (4) develop moduli and strength correlations. An inverse size effect was observed, wherein increasing Ø reduced velocities, moduli, damping, v, and strength. Conversely, increasing ρ_d enhanced mechanical properties, with maximum values at around 70 % S_r. Plasticity index and mineral constituents contributed to the observed nonlinearity in D_smin and D_ucmin. Although Ø and S_r partially contributed, mechanical correlations were primarily influenced by ρ_d under unconfined conditions. Hence, the proposed wave-based equations enable practical assessment of bentonite buffer blocks after production and prior to installation in nuclear waste repositories.

本研究考察了高度压实的膨润土的小应变动态特性和强度，膨润土是韩国工程屏障系统（EBS）的候选缓冲材料。对不同直径尺寸（Ø）、干密度（ρd）和饱和度（Sr）的试件进行了自由-自由共振柱（FFRC）和无侧限压缩试验（UCT）。FFRC测定了剪切、无约束和约束压缩波速（分别为Vs、Vc和Vp）、小应变模量、材料剪切阻尼（Dsmin）和纵向阻尼（Ducmin）。增加Ø， ρd和Sr的影响是利用地震波来研究的(1)确定动力刚度，(2)表征材料阻尼，(3)允许直接计算动力泊松比(v)，以及(4)开发模量和强度相关性。观察到一个逆尺寸效应，其中增加Ø降低速度，模量，阻尼，v和强度。反之，ρd的增加增强了材料的力学性能，在70% sr左右达到最大值。塑性指数和矿物成分导致了Dsmin和Ducmin的非线性。虽然Ø和Sr有部分贡献，但在无约束条件下，ρd主要影响力学相关性。因此，提出的基于波动的方程能够在生产后和核废料库安装之前对膨润土缓冲块进行实际评估。

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引用次数: 0

Enhanced fidelity of Monte Carlo coupled multi-physics simulations in the MCS code 增强的保真蒙特卡罗耦合多物理场模拟在MCS代码

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-12-10 DOI: 10.1016/j.net.2025.104077

Muhammad Imron , Deokjung Lee

This study integrates previously developed methods to enhance the fidelity of direct whole-core Monte Carlo coupled multi-physics simulations in the MCS code. First, it introduces multi-physics simulations with spatially continuous material properties by using the Functional Expansion Tally combined with delta-tracking. Second, it incorporates on-the-fly thermal expansion of reactor core components during Monte Carlo particle tracking. To evaluate the accuracy and overall performance improvement of the framework, several numerical experiments were conducted at both the assembly and whole-core levels. The incorporation of spatially continuous material properties produces eigenvalue solutions that asymptotically converge to those from conventional cell-based discretized simulations with infinitesimally small cells as demonstrated in the assembly and whole-core problems. In the whole-core problem, the framework reduces simulation times by around threefold and requires 80 % less memory than the traditional cell-based discretization using very small cells, while maintaining the high-fidelity solutions. Whereas the numerical results for on-the-fly thermal expansion demonstrate that the observed trends in reactor reactivity due to thermal expansion align with previous studies. These findings suggest that integrating the multi-physics framework into reactor modeling can enhance simulation fidelity while reducing simulation time.

本研究整合了先前开发的方法，以提高MCS代码中直接全核蒙特卡罗耦合多物理场模拟的保真度。首先，利用函数扩展计数法结合delta跟踪，引入了具有空间连续材料属性的多物理场仿真。其次，在蒙特卡罗粒子跟踪过程中，它结合了反应堆堆芯组件的动态热膨胀。为了评估框架的准确性和整体性能改进，在组装和整个核心水平上进行了一些数值实验。空间连续材料特性的结合产生了特征值解，该解渐近收敛于传统的基于单元的离散化模拟，该模拟具有无穷小的单元，如在装配和整个核心问题中所示。在全核问题中，该框架将模拟次数减少了大约三倍，并且比使用非常小的单元的传统基于单元的离散化减少了80%的内存，同时保持了高保真度的解决方案。而动态热膨胀的数值结果表明，观察到的热膨胀对反应堆反应性的影响趋势与前人的研究一致。这些发现表明，将多物理场框架集成到反应堆建模中可以提高仿真保真度，同时减少仿真时间。

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引用次数: 0

Enhanced radioisotope identification via dual-spectrum analysis using scintillation detectors 利用闪烁探测器通过双光谱分析增强放射性同位素鉴定

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2026-01-07 DOI: 10.1016/j.net.2025.104107

Aydin Ghalehasadi , Saleh Ashrafi , Narjes Amiri , Okhtay Jahanbakhsh

Accurate identification of radionuclides in complex mixtures is often hindered by spectral overlap, particularly when using low-resolution detectors. This study presents an enhanced approach that simultaneously utilizes beta and gamma spectra acquired from a dual-detector setup consisting of a plastic scintillator and a NaI(Tl) crystal. Rather than relying solely on gamma peaks, the method incorporates the full beta spectrum as complementary information to improve isotopic separation, especially for radionuclides with closely spaced gamma emissions. Simulated scenarios involving Cs-134 and Cs-137 demonstrate that adding beta data reduces identification error and improves source discrimination. This dual-spectrum strategy offers a practical solution for improving radioisotope identification in portable detection systems used in nuclear safety and environmental monitoring.

在复杂混合物中准确识别放射性核素常常受到光谱重叠的阻碍，特别是在使用低分辨率探测器时。本研究提出了一种增强的方法，同时利用由塑料闪烁体和NaI（Tl）晶体组成的双探测器设置获得的β和γ光谱。该方法不是仅仅依赖于伽马峰，而是结合了完整的β谱作为补充信息，以改善同位素分离，特别是对于具有紧密间隔伽马辐射的放射性核素。Cs-134和Cs-137的模拟场景表明，加入beta数据可以减少识别误差，提高源辨别能力。这种双光谱策略为改进用于核安全和环境监测的便携式探测系统中的放射性同位素识别提供了一种切实可行的解决方案。

引用次数: 0

Challenges and mitigations of corrosion and scale in nuclear cogeneration desalination systems: A case study from West Kalimantan 核热电联产海水淡化系统中腐蚀和结垢的挑战和缓解措施：来自西加里曼丹的案例研究

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-12-24 DOI: 10.1016/j.net.2025.104100

Siti Alimah , Sriyono , June Mellawati , Sudi Ariyanto , Sunarko , Akhmad Muktaf Haifani , Djati Hoesen Salimy , Yuni Indrawati , Khusnul Khotimah

Nuclear power plant cogeneration with Multi-Effect Distillation (MED) offers a solution to provide both electricity and a freshwater supply in West Kalimantan. The influence of tropical seawater quality on the corrosion and scale formation potential and its implications for desalination performance were described. A physicochemical characterization of seawater quality for consistent feedwater is crucial to ensure desalination performance. Results indicated moderate corrosion rates (0.46–0.47 mm/year), driven largely by high chloride concentration, elevated TDS, and near-neutral pH. The content of Fe, Zn and Pb is potentially accelerating corrosion. In contrast, consistently negative LSI values (−1.83 to −2.44) confirmed negligible scaling potential but high corrosivity. Corrosion will accelerate material degradation, reduce thermal efficiency, and decrease the ratio between the amount of distillate produced and steam used. This also impacts the reliability and safety of nuclear installations, which require a freshwater supply for cooling systems. These findings emphasize corrosion as the critical operational challenge and highlight the need for corrosion-resistant materials, protective coatings, cathodic protection, and advanced pretreatment to ensure safe and sustainable MED–nuclear cogeneration systems in coastal environments.

核电站多效蒸馏热电联产（MED）为西加里曼丹提供了电力和淡水供应的解决方案。介绍了热带海水水质对海水腐蚀和结垢潜力的影响及其对海水淡化性能的影响。为了保证海水淡化的性能，一致给水的海水质量的物理化学特性是至关重要的。结果表明，高氯化物浓度、升高的TDS和接近中性的ph值是导致腐蚀速率适中（0.46-0.47 mm/年）的主要原因。铁、锌和铅的含量可能会加速腐蚀。相反，持续负的LSI值（- 1.83至- 2.44）证实了可忽略不计的结垢潜力，但高腐蚀性。腐蚀会加速材料的降解，降低热效率，降低馏出物和蒸汽用量之间的比例。这也影响到核设施的可靠性和安全性，因为核设施的冷却系统需要淡水供应。这些发现强调了腐蚀是关键的操作挑战，并强调了耐腐蚀材料、保护涂层、阴极保护和先进预处理的必要性，以确保沿海环境中MED-nuclear热电联产系统的安全和可持续。

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引用次数: 0

Research on depletion chain simplification method based on pseudo-decay nuclides 基于伪衰变核素的耗尽链简化方法研究

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-12-03 DOI: 10.1016/j.net.2025.104066

Bin Zhang , Xingmin Tang , Lianjie Wang , Xiaojing Liu , Kai Huang , Tengfei Zhang

The applicability of the depletion database determines the accuracy of burnup and power calculations during core simulation. The information of depletion chains in evaluated nuclear databases is unnecessarily complex for most applications in reactor physics, leading to large, rigid, and inefficient burnup matrix. This paper introduces a method for simplifying the depletion chains, which considering the impact of various nuclides and their corresponding transmutation pathways on the calculation accuracy of reactivity rates and nuclide densities. The impact of each reaction channel and decay nuclides is evaluated by depletion calculations of typical problems. Since fission products are intended to be reduced from depletion chains, pseudo-decay nuclides are introduced to substitute the role of fission products to maintain the accuracy of decay heat calculations. The verification results show that the number of nuclides tracked to be reduced from 1500 to 200 or fewer nuclides. No significant deviations are introduced in the calculation of effective multiplication factors and nuclide number densities by the simplified depletion chains. And the pseudo-decay nuclides significantly maintain the accuracy of decay heat calculations, with the deviation of decay heat contribution to total power being less than 0.5 %.

耗尽数据库的适用性决定了堆芯模拟过程中燃耗和功率计算的准确性。在大多数反应堆物理应用中，评估核数据库中的耗尽链信息过于复杂，导致燃耗矩阵大、刚性和低效。本文介绍了一种简化耗尽链的方法，该方法考虑了各种核素及其相应的嬗变途径对反应率和核素密度计算精度的影响。每个反应通道和衰变核素的影响通过典型问题的耗尽计算来评估。由于裂变产物打算从耗尽链中还原，因此引入了伪衰变核素来代替裂变产物的作用，以保持衰变热计算的准确性。验证结果表明，跟踪到的核素数量从1500个减少到200个或更少。简化耗尽链在计算有效增殖因子和核素数密度时没有引入明显的偏差。伪衰变核素保持了衰变热计算的准确性，衰变热对总功率贡献的偏差小于0.5%。

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引用次数: 0

A comparative study on machine learning models for estimating cathode material compositions in black powders using prompt gamma-ray spectra 利用提示伽玛射线谱估计黑粉末正极材料成分的机器学习模型的比较研究

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-12-06 DOI: 10.1016/j.net.2025.104069

Yohan Lee , Byoungil Jeon , Soobin Lim

According to the rapid growth of the Lithium-ion battery (LIB) recycling industry, the demands for rapid and non-destructive analysis of black powder, the key product in this recycling process, has increased to enable effective recovery of valuable materials and the formulation of optimal recycling strategies. This study aims to evaluate the feasibility of a deep learning application that estimates the composition of valuable materials in black powder in prompt gamma-ray activation analysis (PGAA). Reference data for major target materials, Nickel, Cobalt, Manganese, and Iron, were acquired using the Four-circle single-crystal diffractometer at the HANARO research reactor, and synthetic datasets with varying counting statistics were generated for model training. To identify the most suitable model for PGAA-based composition estimation, we conducted a comparative analysis of six machine learning algorithms, including machine learning (Lasso, Decision Tree, XGBoost) and deep learning architectures (MLP, CNN, Transformer). Among them, the Transformer architecture demonstrated best performance, achieving an r² score of over 0.99 for all components. Furthermore, uncertainty quantification using deep ensembles confirmed that the model provides reliable confidence intervals, essential for industrial decision-making. These results demonstrate the promising potential of the deep learning method for effective and high-throughput battery recycling applications.

随着锂离子电池（LIB）回收行业的快速增长，对黑粉这一回收过程中的关键产品进行快速、无损分析的需求日益增加，以实现有价值材料的有效回收和优化回收策略的制定。本研究旨在评估在快速伽马射线激活分析（PGAA）中估计黑火药中有价值物质组成的深度学习应用的可行性。主要目标材料镍、钴、锰和铁的参考数据使用HANARO研究堆的四圆单晶衍射仪获取，并生成具有不同计数统计量的合成数据集用于模型训练。为了确定最适合基于pgaa的成分估计的模型，我们对六种机器学习算法进行了比较分析，包括机器学习（Lasso, Decision Tree, XGBoost）和深度学习架构（MLP， CNN, Transformer）。其中，Transformer体系结构表现出最好的性能，所有组件的r2得分都超过0.99。此外，使用深度集成的不确定性量化证实了该模型提供可靠的置信区间，这对工业决策至关重要。这些结果证明了深度学习方法在有效和高通量电池回收应用中的巨大潜力。

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引用次数: 0

The influence of matrix effect on neutron-neutron angular correlation and energy-angle correlation of special nuclear material 基质效应对特殊核材料中子-中子角关联和能量-角关联的影响

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-11-29 DOI: 10.1016/j.net.2025.104056

Kaile Li, Sufen Li, Xingfu Cai, Yonggang Huo

The fission neutron will show a certain angular correlation due to the momentum enhancement of fission fragments. Neutron-neutron angular correlation is related to the intrinsic characteristics of the nucleus and can be applied to the characterization of nuclear materials. Currently, the mechanism related to the influence of matrix effects on neutron-neutron angular correlation of nuclear materials is not clear, which leads to the deviation. In this paper, a liquid scintillation detection system was built by Geant4 to investigate the matrix effects of nuclear materials. It is found that the change of neutron-neutron angular correlation mainly comes from the effect of induced fission and neutron scattering. Meanwhile, this paper also investigates the neutron anisotropy in different energy regions and the change of neutron-neutron angular correlation, and obtains the distribution of neutron-neutron energy-angle correlation, which further reveals the nature of neutron energy angular correlation. It is shown that neutron-neutron angular correlation is strongly affected by the matrix effect of nuclear materials and cannot be used to characterize the properties of nuclear materials. The neutron-neutron energy-angle correlation achieves feature enhancement by coupling the angle and energy information of fission neutrons, and has great potential in the radionuclide identification. The findings of this study on the matrix effect and the proposed energy-angle correlation analysis have significant potential for application in nuclear security and safeguards.

由于裂变碎片的动量增强，裂变中子将表现出一定的角相关性。中子-中子角相关关系到原子核的固有特性，可以应用于核材料的表征。目前，基体效应对核材料中子-中子角相关的影响机制尚不清楚，从而导致了偏差。本文利用Geant4建立了一个液体闪烁探测系统，用于研究核材料的基质效应。发现中子-中子角相关的变化主要来自诱导裂变和中子散射的影响。同时，本文还研究了中子在不同能量区域的各向异性和中子-中子角相关的变化，得到了中子-中子能量角相关的分布，进一步揭示了中子能量角相关的本质。结果表明，中子-中子角相关受核材料基体效应的影响较大，不能用来表征核材料的性质。中子-中子能量角相关通过耦合裂变中子的角度和能量信息实现特征增强，在放射性核素识别中具有很大的潜力。本文关于矩阵效应的研究结果和提出的能量角相关分析在核安全与保障中具有重要的应用潜力。

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引用次数: 0

One policy to rule them all: Handling multiple emergent accidents in nuclear power plants with ensemble-based behavior cloning 有一项政策可以统治所有人：用基于整体行为克隆的方法处理核电站的多起紧急事故

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2026-04-01 Epub Date: 2025-09-27 DOI: 10.1016/j.net.2025.103932

Aicheng Gong , Mengbei Yan , Shengjie Sun , Kaihe Kong , Jiafei Lyu , Xiu Li

Nuclear energy plays a vital role in the global shift toward sustainable power. Ensuring the safety and efficiency of nuclear power plant (NPP) operations is critically important, especially in the presence of multiple emergent accident scenarios. This highlights a pressing need for a controller capable of automatically and rapidly responding to multiple emergent accidents. To address this, we present a Markov Decision Process (MDP) model tailored to the nuclear power plant environment, focusing on six representative accident conditions. Building on this foundation, we introduce two novel algorithms – Ensemble-based Cross-Task Behavior Cloning (ECT-BC) and Ensemble-based Cross-Task Value-Weighted Behavior Cloning (ECT-VWBC) – which integrate Deep Reinforcement Learning (DRL) and Ensemble Learning to train an agent for handling multiple emergent accidents in NPPs. ECT-BC employs offline imitation learning to train policy models using expert data of numerous emergent accidents simultaneously. ECT-VWBC further introduces a value-based weighting scheme that prioritizes training samples with higher estimated action values, enhancing the influence of optimal actions. We propose ensemble-based methods with a voting mechanism to enhance policy diversity and generalization. Experimental results on the Nuclear Power Plant Accident Conditions MDP demonstrate the effectiveness of our algorithms, providing a foundation for more reliable autonomous decision-making systems in nuclear safety applications.

核能在全球向可持续能源的转变中发挥着至关重要的作用。确保核电站运行的安全和效率是至关重要的，特别是在存在多种紧急事故情景的情况下。这凸显了对一种能够自动快速响应多种紧急事故的控制器的迫切需求。为了解决这个问题，我们提出了一个针对核电站环境的马尔可夫决策过程（MDP）模型，重点关注六种具有代表性的事故条件。在此基础上，我们引入了两种新颖的算法——基于集成的跨任务行为克隆（ECT-BC）和基于集成的跨任务价值加权行为克隆（ECT-VWBC）——它们集成了深度强化学习（DRL）和集成学习来训练智能体处理核电站中的多个紧急事故。ECT-BC采用离线模仿学习，利用大量突发事件的专家数据同时训练策略模型。ECT-VWBC进一步引入了一种基于值的加权方案，该方案优先考虑动作估计值较高的训练样本，增强了最优动作的影响。我们提出了带有投票机制的基于集合的方法来增强政策的多样性和泛化。在核电厂事故条件MDP上的实验结果验证了算法的有效性，为核安全应用中更可靠的自主决策系统提供了基础。

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引用次数: 0