Nuclear Engineering and Technology最新文献

Baseline radiological environmental monitoring and impact assessment of radioactive waste storage facilities in Thailand 泰国放射性废物储存设施的基线辐射环境监测和影响评估

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

Nuclear Engineering and Technology

Pub Date : 2026-02-10 DOI: 10.1016/j.net.2026.104185

Anan O-Manee , Suwisa Sudchawa , Chalit Muanglay , Panuwat Srimork , Archara Phattanasub , Ritiron Samran , Wutthikrai Kulsawat , Phatchada Nochit , Waleeporn Pongkua

Radiation monitoring was conducted at two sites of the RWSF in Thailand. The activity concentration of tritium was assessed in the surface water, while gross alpha/beta radioactivity levels were measured additionally in soil and sediment. Gamma-ray spectroscopy was obtained the radioactivity concentrations for all environmental samples, and the external gamma-ray exposure dose rate was estimated. No tritium activity was detected at either site and showed no influence from nuclear-related activities. The average gross alpha/beta levels were found to be low, approximately 0.06-0.50 Bq/L, indicating that these levels are within safe limits. The activity concentrations of K-40, Th-232, and U-238 radionuclides in soil samples were 239.38 ± 21.75, 57.95 ± 1.56, and 50.34 ± 0.56 Bq/kg, respectively, while those in water samples were 17.15 ± 1.31, 0.69 ± 0.13, 0.32 ± 0.05 Bq/L, respectively. These natural radionuclides do not exceed the recommended limits. Related artificial radionuclides, including Cs-137, Co-60, and I-131 were not detected in any sample. Additionally, no radionuclides were detected in airborne dust samples, possibility of effective air ventilation in the sampling area. Moreover, the external gamma-ray exposure rate approximately 0.3-0.5 μSv/h, within the natural background radiation level. This routine monitoring has been strictly in accordance with international regulations, confirming that the RWSFs pose no radiological risk to nearby living organisms.

辐射监测工作在泰国的两个地点进行。评估了地表水中氚的活度浓度，同时还测量了土壤和沉积物中的总α / β放射性水平。通过伽玛能谱法获得了各环境样品的放射性浓度，并估算了外部伽玛射线照射剂量率。在这两个地点均未检测到氚活性，也未显示出受核相关活动的影响。平均总α / β水平较低，约为0.06-0.50 Bq/L，表明这些水平在安全范围内。土壤样品中K-40、Th-232和U-238放射性核素活性浓度分别为239.38±21.75、57.95±1.56和50.34±0.56 Bq/kg，水样中K-40、Th-232和U-238放射性核素活性浓度分别为17.15±1.31、0.69±0.13、0.32±0.05 Bq/L。这些天然放射性核素没有超过建议限量。在任何样本中均未检测到相关的人工放射性核素，包括Cs-137、Co-60和I-131。此外，在空气中的粉尘样本中未检测到放射性核素，这可能是采样区域有效的空气通风。此外，外部γ射线暴露率约为0.3-0.5 μSv/h，在自然本底辐射水平之内。这一例行监测是严格按照国际规定进行的，证实了再生水处理厂不会对附近的生物构成辐射风险。

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引用次数: 0

Nuclear and radiological characterization of a 226Ra-Be neutron irradiator at INFISA-UNMSM, Peru, using Monte Carlo simulation with the OpenMC code 秘鲁INFISA-UNMSM的226Ra-Be中子辐照器的核和放射特性，使用蒙特卡罗模拟和OpenMC代码

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

Nuclear Engineering and Technology

Pub Date : 2026-02-10 DOI: 10.1016/j.net.2026.104158

P. Tataje , Abdessamad Didi , A. Arroyo , S. Daza

A neutron irradiator consisting of a²²⁶Ra-Be source with a 3 mCi activity of radium, used for the early teaching of neutron activation experiments, belonging to the INFISA-UNMSM, was characterized using the relatively new open-source framework OpenMC. The ²²⁶Ra-Be source is located inside a hermetically sealed nickel-soldered cylinder filled with activated carbon. This cylinder, in turn, is inside a larger cylinder filled with paraffin wax, with seven irradiation channels. These channels were characterized for axial and radial neutron flux, prompt gamma flux, and dose equivalent rate (H∗₍₁₀₎) both inside the irradiation channels and on the exterior of the cylinder.

利用相对较新的开放源代码框架OpenMC对用于中子活化实验早期教学的中子辐照体进行了表征，该中子辐照体由镭活度为3mci的226ra - be源组成。226Ra-Be源位于一个密封的镍焊气缸内，气缸内填充活性炭。这个圆柱体，反过来，是在一个更大的圆柱体充满石蜡，有七个辐照通道。这些通道的特征是轴向和径向中子通量，提示伽马通量和剂量等效率（H *(10)）在辐照通道内和柱体的外部。

引用次数: 0

Deep learning approaches for high-resolution wind data enhancement around a nuclear power plant 核电站周围高分辨率风力数据增强的深度学习方法

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

Nuclear Engineering and Technology

Pub Date : 2026-02-10 DOI: 10.1016/j.net.2026.104186

Dakyoung Lee, Juryong Park, Eung Soo Kim

When radioactive materials are released near nuclear power plants, local wind fields control the dispersion path and concentration distribution. In Korea, complex terrain, sea–land breezes, and seasonal variability amplify prediction uncertainty, underscoring the need for high-resolution wind data. This study proposes and validates a framework that combines physics-based Weather Research and Forecasting (WRF) modeling with deep learning to generate high-resolution winds while lowering computational cost. We employ a Transformer-based Uformer trained on WRF-generated datasets to perform super-resolution of wind fields, addressing the limitations of simple interpolation. To curb storage and data processing burdens from finer grids, we apply Singular Value Decomposition (SVD) for compact, low-loss compression. The super-resolved winds are coupled to a Lagrangian Patricle Dispersion Model (LPDM) to assess dispersion sensitivity and evaluate Uformer fidelity and SVD effectiveness. Experiments show horizontal resolution improved from 1.5 km to 300 m, capturing local flows dominating near-field transport. With SVD, data volume decreases by ∼32% with negligible reconstruction error (

1.2 \times 10^{- 6})

, enabling faster storage and reuse. Overall, the pipeline delivers high-resolution winds more quickly and efficiently than physical modeling, strengthening atmospheric dispersion predictions in complex meteorology typical of Korean nuclear power plant regions and enhancing the timeliness of radiological emergency decision support.

当放射性物质在核电站附近释放时，当地的风场控制着放射性物质的扩散路径和浓度分布。在韩国，复杂的地形、海陆风和季节变化放大了预测的不确定性，强调了对高分辨率风数据的需求。本研究提出并验证了一个框架，该框架将基于物理的天气研究与预报（WRF）建模与深度学习相结合，在降低计算成本的同时生成高分辨率的风。我们使用基于变压器的Uformer训练了wrf生成的数据集来执行风场的超分辨率，解决了简单插值的局限性。为了减少更细网格的存储和数据处理负担，我们应用奇异值分解（SVD）进行紧凑、低损耗的压缩。将超分辨风与拉格朗日粒子色散模型（LPDM）耦合，以评估色散敏感性、Uformer保真度和SVD有效性。实验表明，水平分辨率从1.5 km提高到300 m，捕捉主导近场输送的局地气流。使用SVD，数据量减少了~ 32%，重构误差可以忽略不计（1.2×10−6），从而实现更快的存储和重用。总体而言，该管道比物理建模更快、更有效地提供高分辨率风，加强了韩国核电站地区典型的复杂气象中的大气扩散预测，并提高了辐射应急决策支持的及时性。

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引用次数: 0

Seismic fragility analysis of NPP cabinets considering high-frequency excitations using an efficient numerical model 考虑高频激励的核电厂柜体地震易损性分析

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

Nuclear Engineering and Technology

Pub Date : 2026-02-09 DOI: 10.1016/j.net.2026.104188

Shariful Islam, Towhid Ahmed, Dong Van Nguyen, Dookie Kim

Electrical cabinets are critical for the reliable operation of nuclear power plants (NPPs), yet their seismic fragility under high-frequency ground motions remains insufficiently addressed. This study develops a computationally efficient three-dimensional finite element model for an anchored NPP electrical cabinet that explicitly accounts for excitation frequency relative to cabinet dynamics. The cabinet is idealized with beam and shell elements, while omitted panel masses are represented by an equivalent lumped mass whose location is optimized using Response Surface Methodology. The optimized model reproduces shaking-table-identified fundamental frequencies with a maximum error of 1.99% and accurately matches measured top-of-cabinet acceleration histories. Seismic fragility is evaluated through incremental dynamic analysis using two controlled suites of motions: a low-frequency set dominated below the fundamental mode and a high-frequency set concentrated near the first-mode frequency. High-frequency excitation produces a consistent leftward shift of fragility curves, indicating earlier exceedance of a functional acceleration limit, and reduces the HCLPF capacity by about 22% compared with low-frequency excitation. These findings demonstrate that excitation frequency relative to cabinet dynamics critically influences seismic vulnerability, and neglecting high-frequency effects can yield unconservative capacity estimates. The proposed framework provides an efficient basis for frequency-sensitive seismic fragility evaluation of NPP cabinets.

电气柜是核电站可靠运行的关键，但其在高频地震动下的地震易碎性仍未得到充分解决。本研究开发了一个计算效率高的锚定核电站电气柜三维有限元模型，该模型明确地说明了相对于机柜动力学的激励频率。箱体采用梁和壳单元，而省略的面板质量由等效集总质量表示，其位置使用响应面方法进行优化。优化后的模型以1.99%的最大误差再现了振动台识别的基频，并准确匹配了测量到的机柜顶部加速度历史。地震易损性是通过增量动力分析来评估的，该分析使用两组受控运动：低频组占主导地位，低于基本模态，高频组集中在第一模态频率附近。高频激励产生脆性曲线一致的左移，表明较早超过功能加速度极限，与低频激励相比，HCLPF容量降低了约22%。这些研究结果表明，相对于机柜动力学的激励频率对地震易损性有重要影响，忽略高频效应会产生不保守的容量估计。该框架为核电厂机柜的频率敏感地震易损性评估提供了有效的依据。

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引用次数: 0

Simulating transport of uranium series radionuclides in fractured rock of Beishan area: The use of multi-channel model and the influence of parameters 模拟北山地区裂隙岩中铀系放射性核素输运：多通道模型的应用及参数的影响

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

Nuclear Engineering and Technology

Pub Date : 2026-02-03 DOI: 10.1016/j.net.2026.104182

Shuo Meng , Hai Wang , Longcheng Liu

In this work, the multi-channel model is applied to simulate transport of radionuclides for uranium series in Beishan area of China. In the model, the mechanisms of advection, velocity dispersion, surface retardation, matrix diffusion and sorption, and radioactive decay are considered. The simulation results show that the normalized concentration of U-238 has the largest value of

\sim 10^{- 5}

at about

10^{3}

yr, while the highest concentration of all daughter nuclides is in the range of

\sim 10^{- 12}

. Moreover, it is found that a decrease in mean aperture of the ensemble of channels causes an earlier arrival of U-238, because of the increase of the fluid velocity of each channel. Similarly, a higher mean flowrate or a smaller average width also leads to an earlier arrival. In addition, it is also observed that early-time behaviors are significantly different, provided that the amount of flow-paths is limited. An increased amount will reduce the difference, since the realization mean flowrate is closer to the statistical mean value of the infinite amount case. Likewise, the effect of heterogeneity of rock matrix on radionuclide transport is also dependent on the number of flow-paths.

本文采用多通道模式模拟了中国北山地区铀系放射性核素的输运。在模型中考虑了平流、速度色散、表面延迟、基体扩散和吸附以及放射性衰变等机理。模拟结果表明，铀-238的归一化浓度在约103年时最大，为~ 10−5，而所有子核素的最高浓度在~ 10−12范围内。此外，还发现由于各通道流体速度的增加，通道集合平均孔径的减小会导致U-238提前到达。同样，较高的平均流量或较小的平均宽度也会导致较早到达。此外，我们还观察到，在流道数量有限的情况下，早期行为有显著差异。增加的流量将减小差异，因为实现的平均流量更接近无限大情况下的统计平均值。同样，岩石基质的非均质性对放射性核素输运的影响也取决于流动路径的数量。

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引用次数: 0

Quantitative analysis of grid geometry effects on spatial harmonic imaging–based single-grid phase-contrast X-ray imaging 网格几何对基于空间谐波成像的单网格相衬x射线成像影响的定量分析

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

Nuclear Engineering and Technology

Pub Date : 2026-02-02 DOI: 10.1016/j.net.2026.104179

Seohee Han, Hyunwoo Lim, Jonghyeok Lee, Hyosung Cho

Single-grid phase-contrast X-ray imaging (SG-PCXI) enables simultaneous reconstruction of absorption, phase-contrast, and dark-field images from a single exposure using spatial harmonic imaging (SHI). Although the geometry of X-ray absorbing grids is known to influence imaging performance, its quantitative impact on SHI-based SG-PCXI has not been systematically characterized. This study investigates how the duty cycle (DC) and strip height of a grid affect fringe modulation, harmonic separation, and the resulting phase and dark-field sensitivity. Monte Carlo simulations were performed using the GATE 9.0 platform under controlled conditions (1 μm focal spot size and 10 μm detector pixel size). Increasing the DC from 0.16 to 0.66 improved grid visibility (GV) from 0.25 to 0.91 and the harmonic peak ratio (HPR) from 0.11 to 0.73. Increasing the strip height from 1.5 to 24.1 μm similarly raised GV from 0.09 to 0.91 and the HPR from 0.04 to 0.73. These changes resulted in a substantial increase in the edge signal-to-noise ratio (ESNR), from 5.4 to 32.6, with clearer edge definition in differential phase-contrast images and increased contrast in dark-field images. This work elucidates fundamental relationships between grid geometry, fringe modulation, and SHI performance, providing a quantitative basis for understanding design trade-offs in laboratory-scale SG-PCXI.

单栅格相衬x射线成像（SG-PCXI）能够利用空间谐波成像（SHI）从单次曝光同时重建吸收、相衬和暗场图像。虽然已知x射线吸收网格的几何形状会影响成像性能，但其对基于shi的SG-PCXI的定量影响尚未系统表征。本研究探讨了电网的占空比（DC）和条带高度如何影响条纹调制、谐波分离以及由此产生的相位和暗场灵敏度。在控制条件下（1 μm焦斑尺寸和10 μm探测器像素尺寸），利用GATE 9.0平台进行蒙特卡罗模拟。将直流电压从0.16提高到0.66，电网可见度（GV）从0.25提高到0.91，谐波峰值比（HPR）从0.11提高到0.73。当条带高度从1.5 μm增加到24.1 μm时，GV从0.09提高到0.91，HPR从0.04提高到0.73。这些变化导致边缘信噪比（ESNR）大幅提高，从5.4提高到32.6，差相对比图像的边缘清晰度更清晰，暗场图像的对比度更高。这项工作阐明了网格几何形状、条纹调制和SHI性能之间的基本关系，为理解实验室规模的SG-PCXI的设计权衡提供了定量基础。

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引用次数: 0

Mineralization and radioactive potential of Magal Gebreel rocks, South Eastern Desert, Egypt: Health risk evaluation 埃及东南部沙漠Magal Gebreel岩石的矿化与放射性潜力：健康风险评价

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

Nuclear Engineering and Technology

Pub Date : 2026-01-29 DOI: 10.1016/j.net.2026.104165

Gehad M. Saleh , Basma A. El-Badry , Mabrouk Sami , Tamader Alhazani , Omnia T. Amer , Ioan V. Sanislav , El Saeed R. Lasheen

The present research aims to evaluate the radiation dosages in the Magal Gebreel granitic phases, which encompass monzogranites, alkali feldspar granites, and altered granites (widely exposed along the shear zone). The former rocks have an average of 89.28 ± 23.85 Bqkg⁻¹ for ²³⁸U, 51.71 ± 9.65 Bqkg⁻¹ for ²³²Th, and 995.34 ± 160.21 Bqkg⁻¹ for 40K utilizing the NaI (Tl) analyzer. Alkali feldspar granites have an average of 146.32 ± 46.73 Bqkg⁻¹ for ²³⁸U, 77.57 ± 11.21 Bqkg⁻¹ for ²³²Th, and 1120.54 ± 26 Bqkg⁻¹ for ⁴⁰K. The later (altered granites) have the highest activity concentrations of ²³²Th (avg. 360.57 ± 58.02 Bqkg⁻¹), ⁴⁰K (avg. 1197.23 ± 106.53 Bqkg⁻¹), and ²³⁸U (avg. 3797.50 ± 725.68 Bqkg⁻¹), as well as their summation (avg. 2201.60 ± 250.62 Bqkg⁻¹). It is obvious that the investigated rocks contain increased activity concentrations and therefore fall above the widely accepted worldwide requirements. The results of microscopic and ESEM analysis revealed large assemblages of significant minerals enclosed in the Magal Gebreel rocks such as precious, base metals, accessories, radioactive-bearing, REE-bearing, and Nb-Ta- bearing minerals. Radium equivalent, dose of human body, absorbed dose rate and annualized dosage, excess life-time cancer, coupled with extra radiological characteristics were inferred for these rocks. Given that the measures of most of these criteria are higher than the international average, it is distinct that the tested rocks (certainly altered granites) have a considerable effect on the natural gamma emission released.

本研究旨在评估Magal Gebreel花岗岩相的辐射剂量，包括二长花岗岩、碱长石花岗岩和蚀变花岗岩（沿剪切带广泛暴露）。利用NaI （Tl）分析仪，前者的平均含量为238U 89.28±23.85 Bqkg−1,232Th 51.71±9.65 Bqkg−1,40K 995.34±160.21 Bqkg−1。碱性长石花岗岩238U、232Th和40K的平均含量分别为146.32±46.73 Bqkg−1、77.57±11.21 Bqkg−1和1120.54±26 Bqkg−1。后者（蚀变花岗岩）的活性浓度最高，分别为232Th（平均值为360.57±58.02 Bqkg−1）、40K（平均值为1197.23±106.53 Bqkg−1）和238U（平均值为3797.50±725.68 Bqkg−1）及其总和（平均值为2201.60±250.62 Bqkg−1）。很明显，所调查的岩石含有增加的活动浓度，因此低于世界上广泛接受的要求。显微和ESEM分析结果显示，在Magal Gebreel岩石中包裹着大量的重要矿物，如贵金属、贱金属、附件、含放射性、含ree和含Nb-Ta矿物。推断了这些岩石的镭当量、人体剂量、吸收剂量率和年化剂量、过量寿命癌以及额外的放射学特征。考虑到大多数这些标准的测量都高于国际平均水平，很明显，被测试的岩石（当然是蚀变花岗岩）对自然释放的伽马辐射有相当大的影响。

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引用次数: 0

Small modular reactors (SMRs): Comparison of saturated versus superheated steam Rankine cycle under equal thermodynamic constraints 小型模块化反应堆（SMRs）：在相同热力学约束下饱和与过热蒸汽朗肯循环的比较

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

Nuclear Engineering and Technology

Pub Date : 2026-01-28 DOI: 10.1016/j.net.2026.104161

Gyudong Kim, Yong Jae Chae, Takhyun Chun, Jeong Ik Lee

With part-load operation is increasingly becoming important issue for small modular reactors (SMRs), two secondary Rankine cycles for a 500 MWth pressurized-water-reactor small modular reactor were compared under identical thermodynamic constraints: a saturated-steam cycle with a U-tube steam generator and a superheated-steam cycle with a once-through steam generator were designed under identical primary-side conditions and the same steam-generator pinch-point temperature difference. Moreover, feedwater heaters satisfied fixed terminal temperature difference and drain-cooler approach limits. Part-load performance (25–100 %) was evaluated using the Stodola-based off-design turbine model with wet-steam penalties and steam-generator pressure/temperature programs consistent with each generator type (i.e., constant-average-temperature for the U-tube steam generator; constant-secondary-pressure for the once-through steam generator). High-pressure turbine pressure ratio and the split between reheater bypass and third feedwater-heater extraction were optimized for maximizing net efficiency. Equipment sizing was assessed via total heat-transfer coefficient–area product. Both cycles achieved similar peak net efficiency. The superheated-steam cycle required lower steam mass flow and smaller total heat-transfer coefficient–area product (i.e., UA), indicating a compact power-conversion system. The saturated-steam cycle was slightly superior at full load, whereas the superheated-steam cycle maintained higher efficiency and smaller reheater and extraction-flow variations at part load. These results provide a constraint-matched benchmark for small modular reactor power conversion systems prioritizing compactness and part-load robustness.

随着部分负荷运行日益成为小型模块化反应堆（SMRs）的重要问题，在相同的热力学约束条件下，对500 m压水堆小型模块化反应堆的两个二次朗肯循环进行了比较：在相同的主侧条件和相同的蒸汽发生器点温差下，设计了带u型管蒸汽发生器的饱和蒸汽循环和带一次性蒸汽发生器的过热蒸汽循环。此外，给水加热器满足固定终端温差和排水冷却器接近限制。部分负荷性能（25 - 100%）使用基于stodola的非设计涡轮模型进行评估，该模型具有湿蒸汽惩罚和与每种发生器类型一致的蒸汽发生器压力/温度程序（即u型管蒸汽发生器的平均温度恒定，一次性蒸汽发生器的二次压力恒定）。优化了高压涡轮压比和再热器旁通与第三给水加热器抽汽的分流，使净效率最大化。通过总传热系数面积积来评估设备尺寸。两个循环都达到了相似的峰值净效率。过热蒸汽循环需要更小的蒸汽质量流量和更小的总传热系数-面积积（即UA），表明功率转换系统紧凑。饱和蒸汽循环在满负荷时效率略高，而过热蒸汽循环在部分负荷时效率较高，再热器和抽提流量变化较小。这些结果为优先考虑紧凑性和部分负载鲁棒性的小型模块化反应堆功率转换系统提供了约束匹配基准。

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引用次数: 0

Analytical derivation of steady-state delayed neutron precursor distribution and effective delayed neutron fraction in a molten salt reactor 熔盐堆中稳态延迟中子前体分布和有效延迟中子分数的解析推导

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

Nuclear Engineering and Technology

Pub Date : 2026-01-23 DOI: 10.1016/j.net.2026.104160

Jae Jun Jeong , Yun Je Cho

In liquid-fueled molten salt reactors (MSRs), the nuclear fuel is dissolved in a molten salt mixture that circulates through the primary loop. For system-scale simulations of MSRs, a point kinetics model (PKM) is commonly employed to describe the core neutronic behavior. In this model, flow-related terms are added to the delayed neutron precursor (DNP) balance equation by simplifying the reactor system into two lumped regions - a reactor core and an external loop. This simplified approach is, however, inadequate for a realistic MSR system with complex flow paths. To overcome this limitation, a DNP transport equation can be incorporated into the PKM in place of the DNP balance equation, enabling a more accurate representation of the DNP distribution throughout the reactor system.

In this study, a one-dimensional thermal-hydraulic model is assumed for MSR system simulations, and the axial power distribution in the reactor core is considered to be either uniform or sinusoidal. Analytical solutions to the steady-state DNP transport equation are then derived to obtain one-dimensional DNP profiles in the core and the corresponding effective delayed neutron fraction. These analytical results can serve as reference solutions for verifying thermal-hydraulic system codes developed for MSRs.

在液体燃料熔盐反应堆（MSRs）中，核燃料溶解在通过主回路循环的熔盐混合物中。对于MSRs的系统尺度模拟，通常采用点动力学模型（PKM）来描述堆芯中子行为。在该模型中，通过将反应堆系统简化为堆芯和外环两个集总区域，将流动相关项加入到延迟中子前体（DNP）平衡方程中。然而，这种简化的方法对于具有复杂流路的实际MSR系统来说是不够的。为了克服这一限制，可以在PKM中加入DNP输运方程来代替DNP平衡方程，从而能够更准确地表示整个反应堆系统中的DNP分布。本研究采用一维热-水力模型进行MSR系统仿真，认为堆芯内的轴向功率分布为均匀分布或正弦分布。然后导出稳态DNP输运方程的解析解，得到堆芯内DNP的一维剖面和相应的有效延迟中子分数。这些分析结果可作为验证为msr开发的热液系统规范的参考解决方案。

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引用次数: 0

Long-term corrosion behavior of a cold-spray copper-SiC composite coating for spent nuclear fuel disposal canisters 废核燃料处理罐用冷喷涂铜-碳化硅复合涂层的长期腐蚀行为

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

Nuclear Engineering and Technology

Pub Date : 2026-01-23 DOI: 10.1016/j.net.2026.104159

Minsoo Lee, Junhyuk Jang, Nakkyu Chae, Jin Seop Kim

A novel copper-silicon carbide (Cu-SiC) metal matrix composite (MMC) was fabricated using cold spray coating and evaluated as a corrosion-resistant barrier for spent nuclear fuel disposal canisters. The Cu-SiC MMC exhibited superior properties compared to pure copper, including reduced oxygen content and a more noble corrosion potential. To assess its long-term performance, a 3690-day corrosion test was conducted under simulated deep geological conditions at the KAERI Underground Research Tunnel (KURT), while embedded in Ca-type bentonite and exposed to 70 °C aerobic groundwater. After over a decade, the Cu-SiC MMC showed an average corrosion depth of only 4.02 ± 1.72 μm. The corrosion kinetics followed a distinct “S-shaped” pattern, attributed to long-term changes at the bentonite-copper interface. Post-test characterization, including surface profilometry and FIB-SEM analysis, confirmed that the chemically inert SiC particles effectively acted as a physical barrier, significantly reducing corrosion penetration. These findings demonstrate the excellent durability and corrosion resistance of Cu-SiC MMC, validating its potential for enhancing the long-term integrity of nuclear waste disposal canisters.

采用冷喷涂技术制备了一种新型的Cu-SiC金属基复合材料（MMC），并对其作为乏燃料处理罐的耐腐蚀屏障进行了评价。与纯铜相比，Cu-SiC MMC表现出更优越的性能，包括氧含量降低和更高贵的腐蚀电位。为了评估其长期性能，在KAERI地下研究隧道（KURT）的模拟深层地质条件下进行了3690天的腐蚀测试，同时埋在ca型膨润土中，暴露于70°C的好氧地下水中。10多年后，Cu-SiC MMC的平均腐蚀深度仅为4.02±1.72 μm。腐蚀动力学遵循明显的“s”型模式，归因于膨润土-铜界面的长期变化。测试后的表征，包括表面轮廓分析和FIB-SEM分析，证实了化学惰性的SiC颗粒有效地起到了物理屏障的作用，显著降低了腐蚀渗透。这些发现证明了Cu-SiC MMC优异的耐久性和耐腐蚀性，验证了其提高核废料处理罐长期完整性的潜力。

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