Annals of Nuclear Energy最新文献

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Research on application of heterogeneous resonance Integral for double heterogeneous system 双异质系统的异质共振积分应用研究

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-21 DOI: 10.1016/j.anucene.2024.111051

Shuai Qin , Qian Zhang , Kai Wang , Dong Huang , Song Li , Yuechao Liang

The Double Heterogeneous (DH) system, where fuel particles are randomly dispersed in the non-fissile matrix, is challenging for the reactor physics calculation. The Sanchez-Pomraning method accurately handles the DH system, but integrating it into existing reactor physics code requires code development. This study adopts the Sanchez-Pomraning coupled Ultra-Fine-Group (SP-UFG) slowing-down calculation to generate the heterogeneous Resonance Integral (RI) for DH system treatment with simple volume homogenization. Fully Ceramic Micro-encapsulated (FCM) fuel pin-cells and plates with varying configurations are calculated for verification. Effective cross-sections (XSs) and k_eff calculated by the heterogeneous RI are compared with SP-UFG results. Results show that the maximum bias of XSs and k_eff caused by the XS biases are less than 5% and 200 pcm, respectively. The maximum bias of k_eff when compared with Monte Carlo calculated results is −213 pcm, demonstrating that only considering the DH effect in the resonance energy region is acceptable.

双异质（DH）系统，即燃料颗粒随机分散在非易裂变基质中，对反应堆物理计算具有挑战性。Sanchez-Pomraning 方法能准确处理 DH 系统，但将其集成到现有反应堆物理代码中需要代码开发。本研究采用桑切斯-波姆兰宁耦合超细群（SP-UFG）减速计算，生成异质共振积分（RI），用于 DH 系统的简单体积均质化处理。对不同配置的全陶瓷微胶囊（FCM）燃料针形电池和板进行了计算验证。将异质 RI 计算出的有效截面 (XS) 和 keff 与 SP-UFG 结果进行了比较。结果表明，XSs 和 keff 的最大偏差分别小于 5%和 200 pcm。与蒙特卡洛计算结果相比，keff 的最大偏差为 -213 pcm，这表明只考虑共振能量区域的 DH 效应是可以接受的。

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引用次数: 0

Machine learning-assisted correlations for prediction of fission gas fractions and hydrogen concentration in VVER-1000 fuel 机器学习辅助关联预测 VVER-1000 燃料中的裂变气体分数和氢浓度

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-21 DOI: 10.1016/j.anucene.2024.111073

Yalcin Ilteris Kaan , Khashayar Sadeghi , Seyed Hadi Ghazaie , Ekaterina Sokolova , Victor Modestov , Vitaly Sergeev , Puzhen Gao

This study aims to develop correlations for predicting the fission gas fractions and hydrogen gas concentration during a fuel cycle, using gene expression programming as an evolutionary machine learning approach. The well-known FRAPCON code is used for generating a straightforward dataset under steady-state conditions. The two-step sensitivity analysis is carried out to identify the most influential parameters for correlation development. Wilks’ statistical method is used to generate 59 scenarios to distribute input parameter uncertainties evenly, which leads to a confidence level of 95 %. The mean squared error for xenon, krypton, and helium is 0, while hydrogen exhibited a value of 59.36 since fraction values are between 0 and 1 and concentration ranged from 5 PPM to 200 PPM.

R^{2}

values exceeded 0.97, indicating strong correlation accuracy. The high accuracy achieved from the correlations demonstrates that selecting a 59-sample dataset based on Wilk’s method is sufficient to obtain accuracy exceeding 95 %.

本研究旨在利用基因表达编程作为进化机器学习方法，开发用于预测燃料循环过程中裂变气体分数和氢气浓度的相关性。使用著名的 FRAPCON 代码生成稳态条件下的直接数据集。通过两步敏感性分析，确定对相关性发展最有影响的参数。使用 Wilks 统计方法生成 59 种情景，均匀分布输入参数的不确定性，从而得出 95 % 的置信度。氙、氪和氦的均方误差为 0，而氢的均方误差为 59.36，因为分数值在 0 到 1 之间，浓度范围在 5 PPM 到 200 PPM 之间。R2 值超过 0.97，表明相关精度很高。相关性达到的高精确度表明，根据 Wilk 方法选择 59 个样本数据集足以获得超过 95 % 的精确度。

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引用次数: 0

Designing a combined guide and investigating the role of collimator in neutron intensity uniformity 设计组合导轨并研究准直器在中子强度均匀性中的作用

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-21 DOI: 10.1016/j.anucene.2024.111064

E. Tayebfard, M. Shayesteh, R. Razavi, M. Eshghi

The present study investigates the effect of some geometrical parameters on the performance of the neutron guide system, including the length of the collimator and the angle between successive guides. This study investigates the use of optical components to remove fast neutrons in straight and angled guides, and their role in focusing the neutron beam and increasing the intensity uniformity on the sample. In this research, the McStas code, which was developed with the Monte Carlo method, was used. The effect of the length of the collimator on the creation of a neutron beam with a certain energy, and the uniformity of the intensity of the beam at the sample location have been investigated. For angled guides, the intensity of the neutron beam and its uniformity at the sample location, in terms of the angle of the guides with each other, were calculated using McStas and Vitess codes and the results were compared with each other. Calculations have been done using an americium-beryllium source with an intensity of about 5 Curie. The results show that the combination of two convergent and divergent collimators have greater ability to uniform the neutron intensity than the linear collimator.

本研究调查了一些几何参数对中子导向系统性能的影响，包括准直器的长度和连续导向器之间的角度。本研究调查了在直导和斜导中使用光学元件去除快中子的情况，以及它们在聚焦中子束和提高样品上的强度均匀性方面的作用。在这项研究中，使用了用蒙特卡罗方法开发的 McStas 代码。研究了准直器的长度对产生一定能量的中子束的影响，以及样品位置上中子束强度的均匀性。对于有角度的准直器，使用 McStas 和 Vitess 代码计算了中子束的强度及其在样品位置的均匀性，并将结果进行了比较。计算是使用强度约为 5 居里的镅铍源进行的。结果表明，与线性准直器相比，两个会聚和发散准直器的组合具有更强的均匀中子强度的能力。

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引用次数: 0

Development of a decommissioning waste assessment module for heavy water reactors 开发重水反应堆退役废物评估模块

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-21 DOI: 10.1016/j.anucene.2024.111001

Hyun Young Shin, Kyu Tae Park, Chan Hee Park, Sung Ryul Kim, Jung Min Oh, Ba Ro Lee, Ji Ung Kim, Hye Jin Kim, So Yun Jeong, Wook Jae Yoo

In this study, we developed a Decommissioning Waste Assessment Module (DWAM) for Heavy Water Reactors (HWRs). To evaluate the waste amount of radioactive structures that make up a significant portion of decommissioning waste, we establish a comprehensive DB containing detailed information on the volume, weight, material type, and radioactivity of each decommissioning waste segment. Decommissioning waste assessment algorithms were developed and applied in the proposed module to optimize the calculated results, and their performance was evaluated to ensure accuracy and reliability. The DWAM currently being developed for the Wolsong Unit 1 commercial pressurized heavy water reactor is a technology that has the potential to be utilized not only for domestic reactors but also for reactors worldwide. In addition, the technology is expected to contribute to the development of technology related to the decommissioning of both radioactive and non-radioactive structures.

在本研究中，我们开发了重水反应堆退役废物评估模块（DWAM）。为了评估占退役废物重要部分的放射性结构的废物量，我们建立了一个综合数据库，其中包含每个退役废物部分的体积、重量、材料类型和放射性的详细信息。我们开发了退役废物评估算法，并将其应用于拟议模块中，以优化计算结果，并对其性能进行了评估，以确保准确性和可靠性。目前正在为卧龙一号机组商用压水重水反应堆开发的 DWAM 是一项不仅有可能用于国内反应堆，而且有可能用于全球反应堆的技术。此外，预计该技术将有助于开发与放射性和非放射性结构退役有关的技术。

引用次数: 0

Optimization study of PSF weighting affecting operators’ organizational performance in digital NPPs 影响数字核电站运营商组织绩效的 PSF 权重优化研究

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-20 DOI: 10.1016/j.anucene.2024.111033

Qian Hu, Yongle Zheng, Yanqi Liu

The organizational performance of main control room (MCR) operators is crucial in digital nuclear power plants (NPPs). A comprehensive study determined the weights of performance-shaping factors (PSFs) influencing operators’ organizational performance. Firstly, a questionnaire survey was conducted, and an interval judgment matrix was innovatively established based on the expectation and standard deviation of statistical data acquired. Next, interval hierarchical analysis (IHA) was employed to derive reasonable intervals for each PSF weight. Finally, a hierarchical interval weighting optimization mathematical model was established for high-precision weighting calculation. This method offers a significant reference for optimizing the PSF weighting process. The approach presented in this paper is highly adaptable and provides new technical and theoretical support for the study of weighting theory.

在数字化核电站（NPP）中，主控室（MCR）操作员的组织绩效至关重要。一项综合研究确定了影响操作员组织绩效的绩效塑造因素（PSF）的权重。首先，进行了问卷调查，并根据所获统计数据的期望值和标准差，创新性地建立了区间判断矩阵。其次，采用区间层次分析法（IHA）得出了每个 PSF 权重的合理区间。最后，建立了分层区间权重优化数学模型，用于高精度权重计算。这种方法为优化 PSF 加权过程提供了重要参考。本文提出的方法具有很强的适应性，为权重理论研究提供了新的技术和理论支持。

引用次数: 0

The influence of spatially anisotropic randomness on the solution of one-dimensional stochastic differential and integral equations 空间各向异性随机性对一维随机微分方程和积分方程求解的影响

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-20 DOI: 10.1016/j.anucene.2024.111058

M.M.R. Williams

We demonstrate that the concept of a one-dimensional stochastic problem, in which only the statistical properties of the medium in one direction are used, is an unphysical situation. Even though the statistically averaged quantities, such as mean value and covariance, may depend only on one space dimension, the statistical properties of the medium in the other two directions must be included. A simple example, based on a second order differential equation, is used to illustrate the point and is supported by numerical calculations. The relevance of this matter to radiation and neutron transport in spatially stochastic media is made clear.

我们证明了一维随机问题的概念，即只使用介质在一个方向上的统计特性，是不符合实际情况的。尽管统计平均量（如均值和协方差）可能只取决于一个空间维度，但必须包括介质在其他两个方向上的统计特性。我们用一个基于二阶微分方程的简单例子来说明这一点，并辅以数值计算。这个问题与空间随机介质中的辐射和中子输运的相关性是显而易见的。

引用次数: 0

Active fault tolerant PD control law for PWRs under external disturbance 外部干扰下压水堆的主动容错 PD 控制法

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-20 DOI: 10.1016/j.anucene.2024.111056

Boubacar Kirgni Hamza , Wang Junling , Lasseini Gonga Yahaya Abdoul Razak , Moussa Hassane Ayouba

NPP is a complex time varying nonlinear system that have to operate under severe constraints while complying with safe operating conditions in order to ensure the power demand and prevent the plant from contingent network instability. Towards this goal, this paper proposes the design of active fault tolerant proportional and derivative (PD) control law for Pressurized Water Reactors (PWRs) under external disturbance. To achieve this, the reactor core’s nonlinear dynamic is transformed into input/output (I/O) second-order system with respect to the power level. Based on the new model, a control strategy is proposed that aims to detect, identify, estimate and compensate for actuator faults. The stability of the system is proven using Lyapunov stability theory, where a quadruple Linear Matrix Inequalities (LMIs) system is derived to provide gains for both the control law and observer. Numerical simulations are conducted to assess the performance of the newly built control strategy and a comparison has been made. It follows that the designed controller not only effectively manages faults and external disturbances but also demonstrate exceptional performance when compared to the model-free controller (MFC) and the L₁ adaptive robust controller (L₁ ARC).

核电厂是一个复杂的时变非线性系统，必须在严格的约束条件下运行，同时遵守安全运行条件，以确保电力需求，防止电厂出现突发的电网不稳定情况。为此，本文提出了压水堆（PWR）在外部干扰下的主动容错比例和导数（PD）控制法设计。为此，反应堆堆芯的非线性动态被转换为与功率水平相关的输入/输出（I/O）二阶系统。在新模型的基础上，提出了一种控制策略，旨在检测、识别、估计和补偿执行器故障。利用 Lyapunov 稳定性理论证明了系统的稳定性，并推导出一个四重线性矩阵不等式（LMI）系统，为控制法和观测器提供增益。通过数值模拟评估了新建控制策略的性能，并进行了比较。结果表明，所设计的控制器不仅能有效管理故障和外部干扰，而且与无模型控制器（MFC）和 L1 自适应鲁棒控制器（L1 ARC）相比，表现出卓越的性能。

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引用次数: 0

Conceptual study of subcritical assembly with neutron generator for reactor physics experiments and neutron utilization 带中子发生器的次临界组件概念研究，用于反应堆物理实验和中子利用

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-20 DOI: 10.1016/j.anucene.2024.111039

Hiroshi Nakagomi, Kenichi Yoshioka, Tsukasa Sugita, Haruo Miyadera

In Japan, critical assemblies are regulated under the “Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactions” which provides guidelines for the construction and the operation of nuclear facilities: the core configurations of nuclear experiments are constrained accordingly. In addition, the nuclear facilities are required to comply with strict administrations if the nuclear facilities have more than the certain amount of nuclear fuels. On the other hand, subcritical assemblies are not subjected to the nuclear reactor regulation because the subcritical assemblies are not classified as nuclear reactors. We propose the subcritical assembly with a pulsed accelerator neutron source, which uses nuclear fuels below the regulation amount to ease maintenance and to widen experimental capabilities. Conceptual study of such system was carried out to calculate the deviation between reactivity difference in critical state and that in subcritical state by using the MCNP 6.2 code and the JENDL 4 library. Neutron source multiplication method and pulsed neutron source method were performed. The deviation can be estimated around 10 % by setting detectors in appropriate positions. Additionally, neutron radiography was studied as a simple application. The geometrical shapes of sample rods were seen clearly.

在日本，临界组件受 "核源材料、核燃料材料和反应监管法 "的监管，该法为核设施的建造和运行提供了指导方针：核实验的核心配置受到相应的限制。此外，如果核设施拥有超过一定数量的核燃料，则必须遵守严格的管理规定。另一方面，亚临界组件不受核反应堆管理条例的约束，因为亚临界组件不属于核反应堆。我们建议亚临界组件配备脉冲加速器中子源，使用低于规定数量的核燃料，以方便维护并扩大实验能力。对这种系统进行了概念研究，利用 MCNP 6.2 代码和 JENDL 4 库计算了临界状态和亚临界状态下反应性差异的偏差。采用了中子源倍增法和脉冲中子源法。通过将探测器设置在适当的位置，可以估算出 10 % 左右的偏差。此外，还研究了中子射线照相这一简单应用。样品棒的几何形状清晰可见。

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引用次数: 0

Experimental study on direct contact condensation of steam bubbles with non-condensable gas at high Reynolds numbers 高雷诺数下蒸汽气泡与不凝性气体直接接触冷凝的实验研究

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-19 DOI: 10.1016/j.anucene.2024.111004

Taikun Guo , Junying Hong , Rui Han , Ruifeng Tian , Sichao Tan , Jiming Wen

Direct contact condensation of steam bubbles with non-condensable gas is common in nuclear safety equipment. It was insufficient research on the direct contact condensation heat transfer model of steam bubbles with non-condensable gas at high Reynolds numbers (Re > 22000) in previous works. To study the effect of non-condensable gas on heat transfer of steam–air bubbles at high Reynolds numbers, a high-speed camera was used to capture the behavior of bubbles and used image processing and bubble reconstruction to obtain size and dynamic parameters of bubbles. The size and upward motion behavior of bubbles were analyzed. The heat transfer coefficient during the bubbles condensation experiment were calculated and experimental results were compared with correlations proposed by previous works. In order to better explain the heat transfer characteristics and predict the heat transfer coefficient of bubbles at high Reynolds numbers, a modified heat transfer correlation based on the correlation of rigid sphere was proposed which are functions of bubble Reynolds number, liquid Prandtl number, Jacob number, and dimensionless time. This correlation considers the influence of both forced convection around bubbles and variations in steam fractions on bubble condensation. Comparison of experimental data and the corresponding predicted values shows that the deviation between the experimental data and predicted values is within ± 25 % which indicates the modified correlation accurately predicts the experimental data in this paper.

蒸汽气泡与不凝性气体的直接接触冷凝在核安全设备中很常见。之前的研究对高雷诺数（Re > 22000）下蒸汽气泡与不凝性气体直接接触冷凝传热模型的研究不足。为了研究高雷诺数下不凝性气体对蒸汽-空气气泡传热的影响，利用高速摄像机捕捉气泡的行为，并通过图像处理和气泡重构获得气泡的尺寸和动态参数。分析了气泡的大小和上升运动行为。计算了气泡凝结实验过程中的传热系数，并将实验结果与前人提出的相关系数进行了比较。为了更好地解释高雷诺数下气泡的传热特性并预测其传热系数，提出了一种基于刚性球体相关性的修正传热相关性，该相关性是气泡雷诺数、液体普朗特尔数、雅各布数和无量纲时间的函数。该相关性考虑了气泡周围的强制对流和蒸汽分数变化对气泡冷凝的影响。实验数据与相应预测值的比较表明，实验数据与预测值之间的偏差在 ± 25 % 以内，这表明本文中修改后的相关性能够准确预测实验数据。

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引用次数: 0

Multi-Beam Accelerator-Driven-Systems of Part I: Optimization on Thermal-Hydraulic design of target assembly 多束加速器驱动系统的第一部分：靶组件的热液压设计优化

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2024-11-16 DOI: 10.1016/j.anucene.2024.111052

Xiaobo Li , Xunchao Zhang , Yuanshuai Qin , Yuan He

Integrated target module with a solid beam window, and cooled by reactor primary coolant is a good contender for Accelerator Driven System (ADS) and the cooling of the beam window is a key technique in it. The numerical analysis of two beam profiles (circular/double-circular scan) for the target assembly was performed by computational fluid dynamics (CFD) method, and a combing method was used to optimize the thermal–hydraulic design. The calculation results indicated that a nozzle was required to lower the maximum external surface temperature of the beam window to below 400℃. This can be achieved by reducing the heat deposited densities or increasing the velocity in the main heat deposited zone without enhancing the heat convection at the window surface, this will effectively reduce the temperature, but without increasing the temperature difference in the beam window. The optimization results indicate that the maximum temperature of the beam window is 393.75℃ and 384.94℃ for the circular scan and the double-circular scan, respectively. Additionally, the maximum temperature difference is 23.0℃ and 17.1℃ for the circular scan and the double-circular scan, respectively.

由反应堆一级冷却剂冷却的带有固体光束窗的集成靶组件是加速器驱动系统（ADS）的有力竞争者，而光束窗的冷却是其中的一项关键技术。利用计算流体动力学（CFD）方法对目标组件的两种梁剖面（圆形扫描/双圆形扫描）进行了数值分析，并采用梳理法对热液设计进行了优化。计算结果表明，需要一个喷嘴来降低束窗的最高外表面温度，使其低于 400℃。这可以通过降低主要热沉积区的热沉积密度或提高速度来实现，而不需要加强窗口表面的热对流，这将有效降低温度，但不会增加梁窗口内的温差。优化结果表明，圆扫描和双圆扫描的光束窗口最大温度分别为 393.75℃和 384.94℃。此外，圆扫描和双圆扫描的最大温差分别为 23.0℃和 17.1℃。

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引用次数: 0

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