Nuclear Engineering and Technology最新文献_第9页

Lifetime thermal analysis of the CANDU spent fuel storage canister at the Wolsung site Wolsung 核电厂 CANDU 乏燃料贮存罐的寿命热分析

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

Nuclear Engineering and Technology

Pub Date : 2024-07-18 DOI: 10.1016/j.net.2024.07.041

Tae Gang Lee , Taehyung Na , Byongjo Yun , Jae Jun Jeong

CANDU spent fuels in the Wolsung site have been stored in dry storage systems, such as concrete canisters and modular air-cooled storage system. The primary role of the canister is to ensure the integrity of the fuel during the storage period, which is significantly influenced by temperature. Thus, thermal analysis for the canister's components, especially for fuel cladding, is essential to demonstrate its safety. The thermal analysis has been conducted mainly for predicting the peak cladding temperature (PCT) since high temperature of the fuel can promote oxidation and cracking. As the expiration of storage license approaches, fuel transfer to final disposal should be prepared. This also requires a thermal analysis to predict minimum cladding temperature (MCT), which is related with brittleness. So, it is crucial to accurately predict both PCT and MCT during entire storage period. The cladding temperature is primarily influenced by decay heat and ambient conditions. The lifetime PCT may occur during summer at the beginning of storage, while the lifetime MCT occurs during winter at the end of storage. In this study, we calculated the PCT and MCT during the entire storage period using a realistic thermal analysis model and, subsequently, conducted their uncertainty analysis.

沃尔松厂址的 CANDU 乏燃料一直储存在干式储存系统中，如混凝土罐和模块化空气冷却储存系统。贮罐的主要作用是确保燃料在贮存期间的完整性，而这在很大程度上受到温度的影响。因此，对燃料罐的组件，特别是燃料包层进行热分析，对于证明其安全性至关重要。进行热分析主要是为了预测包壳的峰值温度（PCT），因为燃料的高温会促进氧化和裂解。随着贮存许可证到期日的临近，应准备将燃料转移到最终处置地点。这也需要进行热分析，以预测与脆性有关的最低包层温度（MCT）。因此，准确预测整个贮存期间的 PCT 和 MCT 至关重要。覆层温度主要受衰变热和环境条件的影响。寿命期内的 PCT 可能发生在贮存初期的夏季，而寿命期内的 MCT 则发生在贮存末期的冬季。在本研究中，我们使用一个现实的热分析模型计算了整个贮存期的 PCT 和 MCT，并随后进行了不确定性分析。

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引用次数: 0

Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX 提高蒙特卡罗代码 NECP-MCX 中多组散射矩阵计算的理算效率和精度

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

Nuclear Engineering and Technology

Pub Date : 2024-07-17 DOI: 10.1016/j.net.2024.07.038

Hongchun Wu, Shuai Qin, Yunzhao Li, Jinkang Shi, Qingming He, Liangzhi Cao

Two issues arise in the calculation of the multi-group scattering matrix when employing a continuous-energy Monte Carlo code for generating homogenized multi-group cross-sections. Firstly, the analog estimator is used to evaluate group-to-group elements, which leads to large statistical uncertainty. Secondly, employing the scalar flux as the weighting function in generating the high-order scattering matrix introduces errors in fast reactor calculations. For the first issue, the repeated collision approach and pre-tabulated cross-section approach are adopted to improve the tally efficiency. For the second issue, the average scattering cosine is calculated based on the conservation of the mean square displacement of neutrons, which is then used to correct the first-order self-scattering cross-section. To evaluate the effectiveness of the above approaches, a PWR pin-cell problem and fast reactor core problems are tested. The results demonstrate that: 1) The figure of merit for multi-group scattering matrix calculations was improved by 8–12 times with the pre-tabulated cross-section approach. 2) Biases of k_eff were reduced from over 500 pcm to less than 300 pcm when using the corrected self-scattering cross-section. 3) The corrected self-scattering cross-section also yielded higher accuracy for the assembly power calculations, where the maximum biases are reduced from 5 % to 1 %.

采用连续能量蒙特卡洛代码生成均质化多组截面时，在计算多组散射矩阵时会出现两个问题。首先，使用模拟估计器来评估组对组元素，这会导致很大的统计不确定性。其次，在生成高阶散射矩阵时使用标量通量作为加权函数，会给快堆计算带来误差。针对第一个问题，我们采用了重复碰撞法和预制截面法来提高统计效率。对于第二个问题，根据中子均方位移守恒计算平均散射余弦，然后用于修正一阶自散射截面。为了评估上述方法的有效性，对压水堆针室问题和快堆堆芯问题进行了测试。结果表明1) 采用预先制表的截面方法，多组散射矩阵计算的优越性提高了 8-12 倍。2) 使用校正自散射截面时，偏差从 500 pcm 以上降至 300 pcm 以下。3) 经校正的自散射截面也提高了装配功率计算的精确度，最大偏差从 5% 降至 1%。

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引用次数: 0

Neutron balance approach for inline critical rod position search calculation in Monte Carlo reactor analysis 蒙特卡洛反应堆分析中用于内联临界棒位置搜索计算的中子平衡法

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

Nuclear Engineering and Technology

Pub Date : 2024-07-16 DOI: 10.1016/j.net.2024.07.037

YuGwon Jo, Jaewoon Yoo, Jae-Yong Lim

The critical rod position search has been one of the issues in the Monte Carlo (MC) reactor analysis. This paper proposes a practical and simple approach for the critical rod position search based on the neutron balance equation and the monotonic relation between the control rod absorption rate and the total rod insertion length. The proposed method was implemented in an inline manner within the McCARD, the MC reactor design code, so that the critical rod position is calculated and updated for each fission source iteration. The numerical results in a typical fast reactor problem demonstrate the promising performance of the proposed method in the critical rod position search calculation. Furthermore, the cycle depletion calculation was performed to show the capability of the McCARD to simulate the rodded operation condition. By addressing the critical rod position search problem through the neutron balance approach, the applicability of the MC code in the advanced reactor design will be expanded.

临界棒位置搜索一直是蒙特卡罗（MC）反应堆分析的问题之一。本文基于中子平衡方程和控制棒吸收率与控制棒插入总长度之间的单调关系，提出了一种实用而简单的临界棒位置搜索方法。提出的方法在 MC 反应堆设计代码 McCARD 中以内联方式实施，因此临界棒位置在每次裂变源迭代时都会计算和更新。一个典型快堆问题的数值结果表明，所提出的方法在临界棒位置搜索计算中具有良好的性能。此外，还进行了循环耗尽计算，以显示 McCARD 模拟有杆运行条件的能力。通过中子平衡方法解决临界棒位置搜索问题，将扩大 MC 代码在先进反应堆设计中的适用性。

引用次数: 0

Assessment of environmental hazard impacts in building materials (Marble), Gabal El-Galala El-Bahariya, Northeastern Desert, Egypt 建筑材料（大理石）对环境危害影响的评估，埃及东北部沙漠，Gabal El-Galala El-Bahariya

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

Nuclear Engineering and Technology

Pub Date : 2024-07-16 DOI: 10.1016/j.net.2024.07.005

M.Y. Hanfi , R.M. Abd El Rahman , Mohammad S. Alqahtani

Galala limestone is widely used for construction and ornamental purposes and is known throughout the world under many commercial names, including Galala White, Galala Golden, Galala Creama and Galala Classic. Using a HPGe spectrometer, about 20 samples from the marble building industry were radiometrically analyzed and the gamma radiation emitted by the radionuclides ²³⁸U, ²³²Th and ⁴⁰K was evaluated. The measurements performed showed that the concentrations of these radionuclides were 15 ± 13, 6 ± 4 and 1100 ± 330 Bq kg⁻¹, respectively. It's important to note that all these recorded values do not exceed the internationally reported average levels of 33, 45 and 412 Bq kg⁻¹for each individual element. The annual effective dose (AED) was estimated. The mean value of AED, 0.07 mSv/y, is comparable to the permissible average of 0.07 mSv/y, respectively. The relationship between radionuclides and their radiological hazard characteristics was studied using various multivariate statistical techniques such as Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA). The results indicate that the main contributors to the radiological hazard associated with marble are uranium and potassium. As a result, the use of marble in building materials may not pose a significant risk to public health.

加拉拉石灰石广泛用于建筑和装饰用途，在世界各地有许多商业名称，包括加拉拉白、加拉拉金、加拉拉奶油和加拉拉经典。使用 HPGe 光谱仪对大理石建筑行业的约 20 个样本进行了辐射分析，并对放射性核素 238U、232Th 和 40K 发出的伽马辐射进行了评估。测量结果显示，这些放射性核素的浓度分别为 15 ± 13、6 ± 4 和 1100 ± 330 Bq kg-1。值得注意的是，所有这些记录值均未超过国际报告的平均水平，即每种元素分别为 33、45 和 412 Bq kg-1。对年有效剂量（AED）进行了估算。年有效剂量的平均值为 0.07 毫希沃特/年，与允许的平均值 0.07 毫希沃特/年相当。利用各种多元统计技术，如皮尔逊相关性、主成分分析和层次聚类分析，研究了放射性核素与其辐射危害特征之间的关系。结果表明，造成大理石放射性危害的主要因素是铀和钾。因此，在建筑材料中使用大理石可能不会对公众健康构成重大风险。

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引用次数: 0

Study on the effect of geometry and material property on collapse pressure of a helical steam generator tube under external pressure 研究外压下螺旋蒸汽发生器管的几何形状和材料特性对塌陷压力的影响

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

Nuclear Engineering and Technology

Pub Date : 2024-07-15 DOI: 10.1016/j.net.2024.07.033

Gyo-Geun Youn , Kwanghyun Ahn , Myeong-Woo Lee

In this paper, a numerical study was conducted to analyze the effect of the geometry (tube thickness, ovality, and helical diameter) and material properties of once through steam generator tubes subjected to external pressure on collapse pressure. The outer diameter of the steam generator tube was fixed at 17 mm, and the tube thickness was changed to 2.5 mm, 2.29 mm, and 1.27 mm. Ovality was considered for three cases of 0 %, 4 %, and 8 %, and three cases for helical diameter were considered: 577 mm, 937 mm, and 1297 mm. As material properties, elastic perfectly plastic property that ignores plastic hardening and real material property that reflect plastic hardening were considered. At the helical diameter (D_m/d_o ≥ 34) considered in this paper, the effect of collapse pressure due to helical bending did not appear on ovalities and both material properties. On the other hand, the wall thickness affected the collapse pressures according to the material properties when ovality occurred (>0 %). This is explained because the collapse mechanism varies depending on the thickness.

本文进行了一项数值研究，分析了承受外部压力的一次通过式蒸汽发生器管的几何形状（管厚、椭圆度和螺旋直径）和材料特性对塌陷压力的影响。蒸汽发生器管的外径固定为 17 毫米，管厚分别为 2.5 毫米、2.29 毫米和 1.27 毫米。考虑了 0%、4% 和 8% 三种情况下的椭圆度，以及三种情况下的螺旋直径：577 毫米、937 毫米和 1297 毫米。作为材料属性，考虑了忽略塑性硬化的弹性完全塑性属性和反映塑性硬化的实际材料属性。在本文考虑的螺旋直径（Dm/do ≥ 34）下，螺旋弯曲导致的塌陷压力对椭圆度和两种材料特性都没有影响。另一方面，当出现椭圆度（0%）时，壁厚会根据材料特性影响塌陷压力。这是因为厚度不同，塌陷机理也不同。

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引用次数: 0

“Two-dimensional distribution reconstruction and emittance diagnostics of proton beam phase space using tomography” "利用断层扫描技术对质子束相空间进行二维分布重构和幅射诊断"

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

Nuclear Engineering and Technology

Pub Date : 2024-07-15 DOI: 10.1016/j.net.2024.07.036

Jeong-Jeung Dang , Seunghyun Lee , Han-sung Kim , Hyeok-jung Kwon

A two-dimensional distribution of a proton beam in phase space was reconstructed using beam profile data and a tomography technique in this study. These beam profile data were acquired by a wire scanner under various beam optics conditions, employing an experimental procedure identical, in principle, to the quadrupole magnet (QM) scan method to diagnose beam parameters. According to beam optics, beam profile data measured while changing the QM current is the same as that measured while rotating the beam distribution in the phase space. Thus, the set of the beam profile data can be converted into a sinogram, serving as source data for tomography. A filtered-back-projection (FBP) method is applied to reconstruct the beam distribution from this sinogram. However, if the range and distribution of the rotation angle are not sufficient, the reconstructed distribution data will be inaccurate, which will negatively affect beam parameter evaluation. To solve this limitation, a simulator incorporating the beam optics theory with the tomography was developed to derive an efficient experimental condition. The beam distribution in the phase space was successfully reconstructed, and the beam parameters evaluated from this were also confirmed to match well with the values obtained from the QM scan.

这项研究利用光束剖面数据和层析技术重建了质子束在相空间的二维分布。这些光束剖面数据是在不同的光束光学条件下通过线扫描仪获得的，其实验过程在原理上与诊断光束参数的四极磁体（QM）扫描方法相同。根据光束光学原理，在改变 QM 电流时测量的光束剖面数据与在相空间旋转光束分布时测量的数据相同。因此，光束剖面数据集可以转换成正弦曲线，作为断层扫描的源数据。滤波后投影（FBP）方法可用于从该正弦曲线重建光束分布。然而，如果旋转角度的范围和分布不够充分，重建的分布数据就会不准确，从而对光束参数评估产生负面影响。为了解决这一局限性，我们开发了一种将光束光学理论与层析成像相结合的模拟器，以得出有效的实验条件。相空间中的光束分布被成功重构，由此评估出的光束参数也被证实与 QM 扫描获得的值十分吻合。

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引用次数: 0

A review of COHRISK: Multihazard risk quantification software for nuclear power plants COHRISK：核电厂多重危害风险量化软件综述

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

Nuclear Engineering and Technology

Pub Date : 2024-07-15 DOI: 10.1016/j.net.2024.07.035

Eujeong Choi , Shinyoung Kwag , Jung-Han Kim , Jeong-Gon Ha , Daegi Hahm , Minkyu Kim

A combination of more than one natural hazard can occur simultaneously by their inherent correlation or by coincidence. One well-known multihazard incident, the Tohoku earthquake-tsunami in Japan 2011, led to a core damage accident at the Fukushima Daiichi nuclear power plant (NPP) and caused significant damage to its community. But despite this accident raising significant awareness of multihazard safety in the nuclear safety engineering community, multihazard risk quantification methods and tools for NPPs are relatively less investigated when compared to those for single hazards. At the same time, some multihazard tools developed outside the nuclear engineering industry are inadequate for extension to NPPs because of the complex NPP systems and the response correlation between the systems, structures, and components. To resolve this problem, the authors have been conducting a series of projects on developing a method for multihazard risk quantification of NPP systems and have launched the related quantification software, Combined Hazard RISK (COHRISK). This paper presents a review of COHRISK including its conceptual background, methodology development, architecture, and future work.

一种以上自然灾害的组合可能因其固有的相关性或巧合而同时发生。一个众所周知的多重危害事件是 2011 年的日本东北地震-海啸，它导致福岛第一核电站（NPP）发生堆芯损坏事故，并对其社区造成了重大损失。尽管这次事故提高了核安全工程界对多重危害安全的认识，但与针对单一危害的方法和工具相比，针对核电站的多重危害风险量化方法和工具的研究相对较少。同时，由于核电厂系统复杂，系统、结构和部件之间存在响应相关性，核工程行业以外开发的一些多重危害工具不足以推广到核电厂。为解决这一问题，作者开展了一系列项目，开发核电站系统多危害风险量化方法，并推出了相关量化软件--组合危害风险软件（COHRISK）。本文对 COHRISK 进行了综述，包括其概念背景、方法开发、架构和未来工作。

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引用次数: 0

Mesh morphing-based pre-processing and numerical simulation of blockage accident in lead–bismuth fast reactor fuel assembly 基于网格变形的铅铋快堆燃料组件堵塞事故预处理与数值模拟

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

Nuclear Engineering and Technology

Pub Date : 2024-07-14 DOI: 10.1016/j.net.2024.07.032

Hao Sun, Yong Ouyang, Zihua Liu, Huo Liang, Hanyan Luo, Zhikang Lin

This paper presents a CFD modeling approach for a 19-rod bundle fuel assembly with spiral semi-cylindrical ribs, which potentially can be used for liquid metal cooled fast reactor, as well as a numerical simulation of flow and thermal behavior under partially blocked conditions. The ribs on fuel rod surface are integrally formed with the cladding to enhance heat transfer while preventing detachment. However, the complex channel geometry presents challenges for grid generation, as using a large number of tetrahedral or polyhedral elements would consume significant computational resources. Therefore, this paper proposes a mesh morphing-based pre-processing method to establish a structured hexahedral mesh for such complex geometry. Using this approach, the 19-rods assembly is analyzed, and the result has been verified by conventional mesh scheme as well as experiment.

本文介绍了可用于液态金属冷却快堆的带有螺旋半圆柱形肋条的 19 根棒束燃料组件的 CFD 建模方法，并对部分阻塞条件下的流动和热行为进行了数值模拟。燃料棒表面的肋条与包壳一体成型，在防止脱落的同时增强了传热效果。然而，复杂的通道几何形状给网格生成带来了挑战，因为使用大量四面体或多面体元素会消耗大量计算资源。因此，本文提出了一种基于网格变形的预处理方法，为这种复杂的几何形状建立结构化的六面体网格。利用这种方法分析了 19 根杆件的装配情况，并通过传统的网格方案和实验验证了结果。

引用次数: 0

Feasibility of a position-sensitive Cherenkov radiation detector using a reflector-coated liquid light guide 使用反射器涂层液体光导的位置敏感切伦科夫辐射探测器的可行性

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

Nuclear Engineering and Technology

Pub Date : 2024-07-14 DOI: 10.1016/j.net.2024.07.030

Sangjun Lee, Siwon Song, Jae Hyung Park, Seunghyeon Kim, Hyungi Byun, Jinhong Kim, Seokhyeon Jegal, Bongsoo Lee

In this study, a Cherenkov radiation sensor was developed utilizing a reflector-coated liquid light guide (LLG). In the proposed configuration, a reflector replaced one of the two photomultiplier tubes (PMTs), forming the core sensing element alongside the LLG, with gamma-ray (⁶⁰Co and ¹³⁷Cs) and a beta-ray (⁹⁰Sr) emitters employed to assess its performance as a position-sensitive detector. The time-of-flight method was utilized to determine time differences corresponding to source positions. Position spectra were generated based on these time differences, with the Cherenkov radiation count rates compared across different types of reflectors to identify the optimal choice. We compared position spectra obtained from two PMTs and one PMT with a reflector, confirming the ability to detect multiple sources. Subsequently, each source was positioned perpendicular or parallel to the sensor axis to capture position spectra. The results demonstrate the sensor's potential as a long-distance position-sensitive detector. By leveraging the simplicity of a single PMT system, the proposed sensor facilitates challenging tasks such as pipeline inspection or non-destructive testing of radioactive waste drums.

本研究利用反射器涂层液体光导管（LLG）开发了切伦科夫辐射传感器。在拟议的配置中，反射器取代了两个光电倍增管（PMT）中的一个，与 LLG 一起构成核心传感元件，并使用伽马射线（60Co 和 137Cs）和β射线（90Sr）发射器来评估其作为位置敏感探测器的性能。利用飞行时间法确定与源位置相对应的时间差。根据这些时差生成位置光谱，并比较不同类型反射器的切伦科夫辐射计数率，以确定最佳选择。我们比较了从两个 PMT 和一个带有反射器的 PMT 获得的位置光谱，确认了探测多个源的能力。随后，将每个光源垂直或平行于传感器轴线定位，以捕捉位置光谱。结果证明了传感器作为远距离位置敏感探测器的潜力。通过利用单个 PMT 系统的简易性，所提出的传感器为管道检测或放射性废物桶的无损检测等具有挑战性的任务提供了便利。

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引用次数: 0

A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition 高浓度蒸汽产生条件下铈射流破裂的三维 cfd 模拟

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

Nuclear Engineering and Technology

Pub Date : 2024-07-14 DOI: 10.1016/j.net.2024.07.034

Jeong-Hyun Eom, Ji-Won Choi, Gi-Young Tak, In-Sik Ra, Huu Tiep Nguyen, Hae-Yong Jeong

The complexity of ex-vessel phenomena during a severe accident limits the most previous CFD applications only to hydrodynamic aspects. The present study performs numerical analysis of jet breakup and debris bed formation under intensive steam generation using the STAR-CCM + code. The CFD prediction of the MATE06 experiment demonstrates jet breakup progression patterns consistent to the experiment results. The predicted jet breakup lengths are in good agreement with the MATE 06 data in earlier stage. However, some disparities of the leading-edge position between the MATE 06 and the simulation are predicted in late stage. This is attributed to non-periodic repetitions of the detachment and reattachment of some fragmented segments to the jet column. The difference of frictional force or shear stress between the experiment and CFD simulation also causes uncertainty in the amount of steam generation. In overall, the present study becomes significant to simulate successfully the series of jet breakup process and debris bed formation under intensive steam generation condition. In future studies, it is required to upgrade the current model through more evaluation of experiments and to develop much sophisticated models which provide an enhanced realistic simulation of ex-vessel phenomena.

由于严重事故期间舱外现象的复杂性，以往的 CFD 应用大多仅限于流体力学方面。本研究使用 STAR-CCM + 代码对高强度蒸汽产生下的射流破裂和碎片床形成进行了数值分析。对 MATE06 实验的 CFD 预测显示了与实验结果一致的射流破裂发展模式。预测的射流破裂长度与 MATE06 早期的数据十分吻合。然而，在后期阶段，MATE 06 和模拟预测的前缘位置存在一些差异。这归因于一些碎裂段与喷流柱的分离和重新连接的非周期性重复。实验与 CFD 模拟之间摩擦力或剪应力的差异也会导致蒸汽产生量的不确定性。总之，本研究对于成功模拟高强度蒸汽产生条件下的一系列射流破裂过程和碎片床的形成具有重要意义。在今后的研究中，需要通过更多的实验评估来升级当前的模型，并开发出更复杂的模型，以提供更逼真的舱外现象模拟。

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引用次数: 0