Nuclear Engineering and Technology最新文献_第2页

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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引用次数: 0

Comparative study on thermal creep resistance of arc ion plated and magnetron sputtered Cr coatings on Zircaloy-4 cladding for accident tolerant fuel 耐事故燃料锆-4包层电弧离子镀和磁控溅射Cr涂层耐热蠕变性能的比较研究

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

Nuclear Engineering and Technology

Pub Date : 2026-01-22 DOI: 10.1016/j.net.2026.104148

Jong-Dae Hong , Hongryul Oh , Martin Ševeček , Hyochan Kim , Dong-Joo Kim , Sung Eun Kim

The development of accident tolerant fuel (ATF) claddings, particularly coating techniques, has been encouraged to address the urgent need for improved safety measures. Using the two prominent coating technologies—that is, arc ion plating (AIP) and magnetron sputtering (MS)—pure Cr was coated on Zry-4 claddings, and the effect of the Cr coating on low temperature (≤400 °C) creep behavior was investigated. Moreover, their mechanical performance was compared based on the coating method. Creep tests conducted using internal pressurization methods under constant hoop stresses revealed that the AIP Cr coatings reduced the total creep strain by approximately 43–60 %, whereas the MS Cr coatings exhibited an 18–33 % reduction. These improvements on the creep resistance were attributed to the high elastic modulus and limited plasticity of the Cr layer as well as the compressive residual stresses induced during the deposition process. However, ring compression tests (RCTs) performed after creep deformation showed that the residual ductility, characterized by offset strain, decreased in Cr-coated claddings, most notably in the MS Cr-coated specimens, owing to the intrinsic brittleness of the Cr layer. Experimental findings on thermal creep behaviors suggest that while Cr coatings significantly improved the creep resistance and delay gap closure, their mechanical integrity under irradiation and pellet-to-cladding mechanical interaction conditions must be carefully assessed to ensure long–term fuel performance in ATF systems.

已鼓励发展耐事故燃料包覆层，特别是包覆技术，以解决改进安全措施的迫切需要。采用电弧离子镀（AIP）和磁控溅射（MS）两种主要的涂层技术，在Zry-4包层上镀上纯Cr，并研究了Cr涂层对Zry-4包层低温（≤400℃）蠕变行为的影响。并基于涂层法对其力学性能进行了比较。在恒定环向应力下，采用内加压方法进行的蠕变试验表明，AIP Cr涂层可将总蠕变应变降低约43 - 60%，而MS Cr涂层则可降低18 - 33%。这些抗蠕变性能的提高是由于Cr层的高弹性模量和有限塑性以及沉积过程中产生的残余压应力。然而，在蠕变变形后进行的环压缩试验（rct）表明，由于Cr层的固有脆性，Cr包覆层的残余延展性（以偏应变为特征）下降，尤其是在MS Cr包覆试件中。热蠕变行为的实验结果表明，尽管Cr涂层显著提高了抗蠕变性能和延迟间隙闭合性，但必须仔细评估其在辐照和球团-包层力学相互作用条件下的机械完整性，以确保ATF系统中的长期燃料性能。

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引用次数: 0

EEMD analysis of unsteady pressure pulsations of a high-pressure reactor circulating pump under off-design working conditions 高压反应堆循环泵非定常压力脉动的EEMD分析

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

Nuclear Engineering and Technology

Pub Date : 2026-01-22 DOI: 10.1016/j.net.2026.104146

Ning Zhang , Jiaqing Chen , Hui Liu , Mona Gad , Bo Gao

High-pressure reactor circulating pumps are widely used in nuclear power systems to maintain the cooling circulation of reactors and serve as the primary loop pump. Rotating stall is likely to occur under low flow conditions, posing a risk to system stability and safety. In this study, the evolution of rotating stall under low flow conditions was investigated using DDES and high-frequency pressure pulsation measurements. The pressure pulsation spectra were analyzed through the improved EEMD. TKE and FEL were used to evaluate energy dissipation inside the pump. Results show that pressure pulsation energy increased rapidly under off-design conditions. At the critical stall condition (0.36Φ_N), the amplitude of f_BPF increased to three times its design value, and the RMS∗ value in the 0-f_R band nearly doubled. According to the EEMD results, the dominant mode IMF₇ has an instantaneous frequency consistent with f_BPF, during stall, with the low-frequency mode IMF₁₃ surging by 289 % under deep stall conditions. Intense turbulent pulsations are induced by the interaction between secondary backflow at the impeller outlet and main flow. Regions of high TKE and FEL are formed at the guide vane inlet and extend into the impeller channel, leading to significant energy dissipation. This is identified as the main cause of the increased amplitude of the f_BPF at the part load conditions. This study provides insights into a better understanding of pressure pulsations and complex flow structures of the impeller/diffuser matched reactor circulating pump.

高压反应堆循环泵广泛应用于核电系统中，是维持反应堆冷却循环的主回路泵。在低流量工况下容易发生旋转失速，对系统的稳定性和安全性构成威胁。在本研究中，采用DDES和高频压力脉动测量研究了低流量条件下旋转失速的演变。通过改进的EEMD分析了压力脉动谱。采用TKE和FEL对泵内能量耗散进行了评价。结果表明，在非设计工况下，压力脉动能量迅速增大。在临界失速状态下（0.36ΦN）， fBPF的幅值增加到设计值的3倍，0-fR波段的RMS∗值几乎增加了一倍。根据EEMD结果，在失速过程中，主导模式IMF7具有与fBPF一致的瞬时频率，而低频模式IMF13在深度失速条件下飙升289%。叶轮出口二次回流与主流的相互作用引起了强烈的湍流脉动。高TKE和FEL区域在导叶入口处形成并延伸到叶轮通道，导致显著的能量耗散。这被认为是部分载荷条件下fBPF振幅增加的主要原因。该研究有助于更好地理解叶轮/扩散器匹配反应器循环泵的压力脉动和复杂流动结构。

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引用次数: 0

Enhancing quality control in radiography systems through automated algorithms 透过自动演算法，加强射线照相系统的品质控制

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

Nuclear Engineering and Technology

Pub Date : 2026-01-22 DOI: 10.1016/j.net.2026.104156

Herdi Firdaus Jamal , Mohammad Wasef Marashdeh , Muhammad Kabir Abdulkadir , Mohd Ilyas Sazali , Hanan Fawaz Akhdar , Muhamad Zabidi Ahmad , Mohd Zahri Abdul Aziz

Quality control (QC) in radiography systems is essential for ensuring imaging accuracy and radiation safety. Traditional QC methods are time-consuming and prone to human error. Automated algorithms offer a potential solution by streamlining QC assessments. The aim of this study was to develop and evaluate the performance of an automated QC algorithm tailored for radiography systems in accordance with Malaysian regulatory requirements by comparing its efficiency, accuracy, and reliability against manual methods. QC algorithms were developed using Microsoft Excel for a comprehensive list of QC tests delineated by the Ministry of Health, Malaysia. These algorithms were designed to automate the input of measured data, execute necessary calculations, and deliver a pass/fail outcome based on established regulatory criteria. The performance of the algorithms was evaluated through data collected from 100 radiography machines across various locations and models. The study compared the time efficiency, accuracy and errors of algorithm-based QC assessments and manual calculations. The algorithm significantly (p < 0.001) reduced QC assessments time by 90 % and eliminated all calculation errors, outperforming manual assessments that occurred 64 times. This is the first Excel-based QC algorithm validated against Malaysian regulations, providing low-cost alternative to commercial systems.

射线照相系统的质量控制（QC）对于确保成像精度和辐射安全至关重要。传统的质量控制方法耗时长，容易出现人为错误。自动化算法通过简化QC评估提供了一个潜在的解决方案。本研究的目的是根据马来西亚的监管要求，通过将其效率、准确性和可靠性与手动方法进行比较，开发和评估为放射照相系统量身定制的自动QC算法的性能。QC算法是使用Microsoft Excel开发的，用于马来西亚卫生部划定的QC测试的综合清单。这些算法旨在自动输入测量数据，执行必要的计算，并根据既定的监管标准提供合格/不合格的结果。通过从不同地点和型号的100台x光机收集的数据来评估算法的性能。该研究比较了基于算法的QC评估和人工计算的时间效率、准确性和误差。该算法显著（p < 0.001）减少了90%的QC评估时间，消除了所有的计算错误，优于64次的人工评估。这是第一个根据马来西亚法规验证的基于excel的QC算法，为商用系统提供了低成本的替代方案。

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引用次数: 0

Neutronic analysis of an EPR core employing PaO2 and NpO2 as burnable absorber coatings 采用PaO2和NpO2作为可燃吸收涂层的EPR堆芯的中子分析

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

Nuclear Engineering and Technology

Pub Date : 2026-01-22 DOI: 10.1016/j.net.2026.104151

S.M. Nymul Hasan Anik, Ali Mahdi, Saad Islam, Mohammad Monzur Hossain Khan, Swarna Sarker Toma

This study investigates the use of Protactinium oxide (PaO₂) and Neptunium oxide (NpO₂) as regenerative burnable-absorber coatings for improving long-cycle reactivity control in a European Pressurized Reactor (EPR) fuel core. The proposed concept applies thin PaO₂ and NpO₂ layers to (Th-²³³U)O₂ Integral Fuel Burnable Absorber (IFBA) fuel rods and evaluates their neutronic performance relative to conventional UO₂+Gd₂O₃ and (Th-²³³U)O₂+Gd₂O₃ (thorium-based) reference designs. Using the full-core SERPENT continuous-energy Monte Carlo code simulations, key parameters including burnup behavior, fissile-inventory retention, neutron-flux spectrum, radioactivity buildup, and actinide/fission-product evolution are assessed. Safety-related indicators such as fuel-temperature, moderator-temperature, and boron-worth coefficients are also examined to determine the impact of regenerative transmutation on inherent stability. The results show that, although the coated cases exhibit higher BOC k_eff than the Gd-bearing reference cores (because the coated designs are gadolinia-free), PaO₂/NpO₂ coatings produce a steeper early-cycle reactivity burn-down and reduce the overall reactivity swing, while sustaining higher reactivity at extended burnup through in-situ formation of ²³³U and ²³⁹Pu. These coatings promote smoother power distribution, stronger boron worth, and reduced reactivity swing compared with Gd-bearing fuel, while yielding lower cumulative radioactivity. Overall, the findings indicate that PaO₂ and NpO₂ coatings offer a promising pathway for enhancing fuel-cycle economy, safety coefficients, and reactivity management in Generation III+ light-water-reactor cores.

本研究研究了使用氧化镤（PaO2）和氧化镎（NpO2）作为再生可燃吸收涂层，以改善欧洲压堆（EPR）燃料堆芯的长周期反应性控制。提出的概念将薄PaO2和NpO2层应用于（Th-233U）O2整体燃料可燃吸收器（IFBA）燃料棒，并评估其相对于传统UO2+Gd2O3和（Th-233U）O2+Gd2O3（钍基）参考设计的中子性能。利用全核SERPENT连续能量蒙特卡罗代码模拟，评估了包括燃烧行为、裂变库存保留、中子通量谱、放射性积累和锕系元素/裂变产物演化在内的关键参数。还检查了与安全相关的指标，如燃料温度、缓和剂温度和硼值系数，以确定再生嬗变对固有稳定性的影响。结果表明，尽管包覆后的样品比含钆参考样品表现出更高的BOC keff（因为包覆后的样品不含钆），但PaO2/NpO2包覆后的早期反应性燃烧更剧烈，总体反应性波动更小，同时通过原位生成233U和239Pu，在延长燃烧时保持更高的反应性。与含gd燃料相比，这些涂层促进了更平滑的功率分配，更强的硼值，减少了反应性波动，同时产生更低的累积放射性。总体而言，研究结果表明，PaO2和NpO2涂层为提高第三代+轻水堆堆芯的燃料循环经济性、安全系数和反应性管理提供了一条有希望的途径。

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引用次数: 0

Frequency Reduction and Order Elevation (FROE): A physics-informed deep learning method for ultra-fine group resonance self-shielding in heterogeneous systems 频率降低和阶次提升（FROE）：一种基于物理的深度学习方法，用于非均质系统中的超细群谐振自屏蔽

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

Nuclear Engineering and Technology

Pub Date : 2026-01-20 DOI: 10.1016/j.net.2026.104150

Dong Liu , Chao Wu , Qi-Long Chen , Kang-Jun He , Jin-Chao Zhang , Qian Zhang , Kai Wang , Chen Zhao , Yang Liu

Resonance self-shielding calculation in complex heterogeneous geometries is essential for reactor physics and core design. While the ultra-fine group method solves the neutron slowing-down equation with high accuracy, its adoption has been limited by low computational efficiency and geometric constraints. Recent progress in deep learning has demonstrated strong potential in neutron transport calculations, offering new solutions to longstanding challenges in resonance self-shielding. This paper proposes a novel deep learning method termed “Frequency-Reduction and Order-Elevation(FROE)." First, frequency reduction is achieved by defining a composite function as the product of the slowing-down spectrum and the total cross-section. This transformation effectively smooths high-frequency oscillations induced by resonance peaks, facilitating neural network approximation. Second, order elevation involves reformulating the integro-differential slowing-down equation into an exact differential form by converting integral terms into their corresponding antiderivatives, thereby improving computational efficiency. Deep neural networks are then employed to represent the composite function and the antiderivatives. The slowing-down equation is solved by training the networks through an alternating iterative scheme to minimize this loss function. Numerical results for several heterogeneous problems, including cases with multi-nuclide resonance interference, validate the proposed method. Our approach accurately yields continuous slowing-down spectra in both space and energy. This work opens a promising new avenue for tackling the enduring challenge of resonance self-shielding in reactor physics.

复杂非均质几何中的共振自屏蔽计算对于反应堆物理和堆芯设计是必不可少的。超细群法求解中子慢化方程的精度较高，但由于计算效率低和几何约束，限制了其应用。深度学习的最新进展在中子输运计算中显示出强大的潜力，为共振自屏蔽领域长期存在的挑战提供了新的解决方案。本文提出了一种新的深度学习方法，称为“频率降低和阶数提升（FROE）”。首先，通过定义一个复合函数作为减速谱和总横截面的乘积来实现频率降低。这种变换有效地平滑了共振峰引起的高频振荡，便于神经网络逼近。其次，阶提升涉及通过将积分项转换为相应的不定积分项，将积分-微分减速方程重新表述为精确的微分形式，从而提高计算效率。然后利用深度神经网络来表示复合函数和不定积分。通过交替迭代的方法来训练网络以最小化损失函数来求解减速方程。对多核素共振干扰等非均质问题的数值计算结果验证了该方法的有效性。我们的方法精确地在空间和能量上产生连续的减速光谱。这项工作为解决反应堆物理中共振自屏蔽的长期挑战开辟了一条有希望的新途径。

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引用次数: 0

Preparation and characterization of metakaolin-based Ag0-containing sorbent beads for iodine capture 偏高岭土基含ag0吸附珠的制备及性能研究

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

Nuclear Engineering and Technology

Pub Date : 2026-01-19 DOI: 10.1016/j.net.2026.104149

Jae Won Lee, Byoungjin So, Seok-Min Hong, Namcheol Kim, Ju Ho Lee, Yung Zun Cho, Chang Hwa Lee

We report metakaolin (MK)-based sorbents with high metallic silver(Ag⁰) content for maximizing iodine uptake per unit volume. Spherical beads were fabricated by a droplet method using slurries with various Na/M (M = Na + Al + Si) and H₂O/Na₂O molar ratios. Subsequent Ag/Na ion exchange and thermal reduction produced Ag⁰-loaded beads with a dense outer layer and porous core. Increasing the Na/M ratio enhanced the maximum silver loading, total iodine capture capacity, and packing density, while the crushing strength decreased with increasing Na/M and H₂O/Na₂O ratios. The resulting Ag⁰MK sorbents exhibited pore sizes larger than the kinetic diameters of relevant iodine species (I₂, HI, CH₃I). As a result, their gravimetric iodine uptake reached 0.612 g-I/g-sorbent, demonstrating high efficiency. These findings suggest that Ag⁰MK sorbents are highly effective for iodine capture and hold strong potential for application in off-gas treatment in nuclear fuel reprocessing and reactor systems.

我们报道了高金属银（Ag0）含量的偏高岭土（MK）基吸附剂，可以最大限度地提高单位体积的碘吸收率。采用不同Na/M （M = Na + Al + Si）和H2O/Na2O摩尔比的浆料，采用液滴法制备了球形微球。随后的Ag/Na离子交换和热还原产生了具有致密外层和多孔核的ag0负载珠。增大Na/M比可提高最大载银量、总碘捕获能力和堆积密度，但破碎强度随Na/M比和H2O/Na2O比的增大而降低。所得Ag0MK吸附剂的孔径大于相关碘（I2， HI, CH3I）的动力学直径。吸附剂的重量碘吸收量达到0.612 g-I/g，吸附剂的吸收率较高。这些发现表明Ag0MK吸附剂对碘的捕获非常有效，在核燃料后处理和反应堆系统的废气处理中具有很大的应用潜力。

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引用次数: 0

Computational retrospective dosimetry with fortuitous dosimeters: An inter-laboratory comparison and evaluation of dose conversion coefficients 随机剂量计的计算回顾性剂量学：剂量转换系数的实验室间比较和评估

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

Nuclear Engineering and Technology

Pub Date : 2026-01-19 DOI: 10.1016/j.net.2026.104152

Min Chae Kim , Hyoungtaek Kim , Yoomi Choi , Sora Kim , Jungil Lee , Byung Il Min , Kyungsuk Suh , Jiyoon Kim , Hanjin Lee , Jeong Tae Lee , Hyungjoon Yu , Young-su Kim , Han Sung Kim , Chan Hyeong Kim

In large-scale radiological accidents, retrospective dose assessment is crucial for individuals without personal dosimeters. This study investigates the applicability of computational dosimetry and dose conversion coefficients (DCCs) using mobile phones as fortuitous dosimeters. A realistic exposure scenario was created using anthropomorphic phantoms and an Ir-192 source. Monte Carlo simulations were performed by three institutions in the Korea Retrospective Dosimetry network (KREDOS), applying ICRP mesh-type reference computational phantoms to estimate whole body dose (WBD) and effective dose (ED). Inter-laboratory comparisons showed z-scores less than 2 for all participants, confirming consistency in computational methods. To validate DCCs, WBDs were reconstructed from mobile phone measurements using both generalized (DCC_ge) and individual (DCC_in) coefficients, and compared with simulated reference doses (WBD_sim). DCC-derived WBDs showed overall improved agreement with WBD_sim at the chest and hip attachment positions compared to direct mobile phone dose measurements. For instance, at the chest position, mobile phone doses overestimated WBD_sim by up to a factor of 2.46, whereas WBD_in (DCC_in-derived WBD) and WBD_ge (DCC_ge-derived WBD) were improved to ranges of 0.75–1.36 and 1.57–2.17 times WBD_sim, respectively. At the hip position under AP irradiation, mobile phone doses corresponded to only 25–36 % of WBD_sim, while WBD_in and WBD_ge approached the reference values at 94–109 % and 71–102 %, respectively.

在大规模放射事故中，回顾性剂量评估对于没有个人剂量计的个人至关重要。本研究探讨了计算剂量学和剂量转换系数（DCCs）使用手机作为偶然性剂量计的适用性。使用拟人化的幽灵和Ir-192源创建了一个真实的暴露场景。韩国回顾性剂量学网络（KREDOS）的三个机构进行了蒙特卡罗模拟，应用ICRP网格型参考计算模型来估计全身剂量（WBD）和有效剂量（ED）。实验室间比较显示，所有参与者的z分数都小于2，证实了计算方法的一致性。为了验证dcc，使用广义（DCCge）和个体（DCCin）系数从手机测量中重建wbd，并与模拟参考剂量（WBDsim）进行比较。与直接移动电话剂量测量相比，dcc衍生的wbd在胸部和臀部附着位置与WBDsim的总体一致性有所提高。例如，在胸部位置，手机剂量对WBDsim的高估高达2.46倍，而WBDin （dccin衍生的WBD）和WBDge （dccge衍生的WBD）分别提高到0.75-1.36和1.57-2.17倍。在AP照射下的髋部位置，手机剂量仅对应WBDsim的25 - 36%，而WBDin和WBDge分别接近参考值的94 - 109%和71 - 102%。

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