Nuclear Engineering and Technology最新文献_第4页

Development of frictional pressure drop models for single- and two-phase flows in a helically coiled tube 螺旋管内单相和两相流动摩擦压降模型的建立

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

Nuclear Engineering and Technology

Pub Date : 2026-01-12 DOI: 10.1016/j.net.2026.104134

Oktari Zaidi, Byong Jo Yun, Jae Jun Jeong

Helically coiled tubes (HCTs) are widely employed in small modular reactors (SMRs), due to their compact geometry and superior heat transfer performance. Accurate prediction of frictional pressure drop for single-phase and two-phase flows in HCTs is crucial for the design and safety analysis of SMRs. In this study, the characteristics of frictional pressure drop in HCTs were investigated using an experimental database comprising 1489 single-phase and 876 two-phase data points. A systematic physics-based model development framework was applied, including key parameters identification and statistically supported modeling to ensure the significance and independence of all selected parameters. Through this, dominant factors influencing frictional pressure drop in HCTs were determined. It was found that, in addition to the well-known flow variables, centrifugal force induced by main axial flow has a significant impact on pressure drop. Based on the finding, new empirical correlations were developed by explicitly incorporating a dimensionless centrifugal force number. The final formulation is designed to preserve asymptotic consistency with straight tube when the curvature effect vanishes. Assessment results indicate that the proposed correlations reduce the root mean square errors by 7.0 %, 9.1 %, and 15.0 %, respectively, compared to the best-performing existing models for single-phase laminar, single-phase turbulent, and two-phase flows.

螺旋盘管（hct）由于其紧凑的几何结构和优越的传热性能而广泛应用于小型模块化反应器（smr）中。准确预测高压混凝土中单相流和两相流的摩擦压降对小型反应器的设计和安全性分析至关重要。在这项研究中，使用包含1489个单相和876个两相数据点的实验数据库研究了hct的摩擦压降特性。采用了系统的基于物理的模型开发框架，包括关键参数识别和统计支持建模，以确保所选参数的重要性和独立性。由此确定了影响hct摩擦压降的主要因素。研究发现，除了众所周知的流量变量外，主轴流引起的离心力对压降也有显著的影响。基于这一发现，通过明确地纳入无量纲离心力数，开发了新的经验相关性。最后的公式被设计成在曲率效应消失时与直管保持渐近一致性。评估结果表明，与现有的单相层流、单相湍流和两相流的最佳模型相比，所提出的相关性分别将均方根误差降低了7.0%、9.1%和15.0%。

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引用次数: 0

Preliminary design and neutronic analyses of ECRH equatorial launcher toward CFEDR ECRH赤道发射装置的初步设计与中子分析

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

Nuclear Engineering and Technology

Pub Date : 2026-01-12 DOI: 10.1016/j.net.2026.104135

Chao Xu , Ming Gao , Yuanyuan Kuang , Dingzhen Li , Chao Zhang , Hanlin Wang , Nengtao Zhou , Shanliang Zheng , Yunying Tang , Xiaojie Wang

Electron Cyclotron Resonance Heating (ECRH) is one of the most important heating systems to maintain long pulse and high-power steady-state operation of fusion reactors. In the recent progress of the ECRH system for the China Fusion Engineering Demonstrator Reactor (CFEDR), the launcher must adopt a modular design while maintaining total mass below the limit for remote handling (RH) maintenance requirements. A drawer-type launcher in the fusion reactor environment has been designed. The equatorial launcher (EL) is composed of two main parts: shielding unit and optical unit containing drawer-type millimeter-wave transmission components. These units form a unified port plug structure. The nuclear analysis of the EL based on the preliminary design has been completed. While satisfying radiation shielding requirements, the optimal thickness of shielding components within the drawer is computationally determined to minimize the launcher's total mass. A double labyrinth shielding configuration is implemented at the gap between launcher and vacuum vessel, with simulation results demonstrating effective suppression of neutron streaming along the gap toward the rear launcher section. The radiation damage to various launcher components is quantified to provide critical data for the structural design and lifetime evaluation.

电子回旋共振加热（ECRH）是维持核聚变反应堆长脉冲、大功率稳态运行的重要加热系统之一。在中国聚变工程示范反应堆（CFEDR）的ECRH系统的最新进展中，发射器必须采用模块化设计，同时保持总质量低于远程处理（RH）维护要求的限制。设计了一种用于聚变反应堆环境的抽屉式发射装置。赤道发射装置（EL）主要由两部分组成：屏蔽单元和包含抽屉式毫米波发射元件的光学单元。这些单元形成一个统一的端口插头结构。在初步设计的基础上，完成了电火花炉的核分析。在满足辐射屏蔽要求的同时，计算确定了抽屉内屏蔽部件的最佳厚度，以使发射器的总质量最小。在发射装置与真空容器之间的间隙处采用了双迷宫式屏蔽结构，仿真结果表明，在发射装置与真空容器之间的间隙处有效地抑制了中子向发射装置后部的流动。对各种发射部件的辐射损伤进行了量化，为结构设计和寿命评估提供了关键数据。

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引用次数: 0

Integrated the Rupture Disk Corrosion Test (RDCT) and Finite Element Analysis (FEA) approach for evaluating PWSCC initiation in Alloy 600 under simulated pressurized water reactors conditions 结合破裂盘腐蚀试验（RDCT）和有限元分析（FEA）方法，在模拟压水堆条件下对Alloy 600的PWSCC起始进行了评估

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

Nuclear Engineering and Technology

Pub Date : 2026-01-12 DOI: 10.1016/j.net.2026.104138

Siyoung Choi , Sung-Woo Kim , Sangtae Kim , Minsung Hong

In this study, the rupture disk corrosion test (RDCT) was employed to measure the initiation time of primary water stress corrosion cracking (PWSCC) in Alloy 600. The applied stress was controlled by the disk specimen thickness, and the PWSCC initiation times were measured experimentally according to the controlled applied stress. Additionally, an optimized finite element analysis (FEA) model was selected to evaluate the applied stress and calculate the stress distribution on the specimen. A clear correlation was established between the applied stress and the PWSCC initiation time; specifically, the initiation time decreased as the applied stress increased. To improve the accuracy and reliability of PWSCC initiation time measurement by RDCT and the stress calculation by FEA, the experimental apparatus was modified, with the computational models were optimized, respectively. This study demonstrates that the integrated RDCT–FEA approach can effectively predict PWSCC initiation under simulated PWR conditions.

本研究采用破裂盘腐蚀试验（RDCT）测量了600合金初次水应力腐蚀开裂（PWSCC）的起始时间。施加的应力由圆盘试样厚度控制，并根据控制的施加应力测量PWSCC的起始时间。此外，选取优化后的有限元分析模型对外加应力进行评估，并计算试件上的应力分布。外加应力与PWSCC起始时间之间存在明显的相关性；随着外加应力的增加，起始时间逐渐缩短。为了提高RDCT法测量PWSCC起始时间和有限元法计算应力的准确性和可靠性，对实验装置进行了改进，并对计算模型进行了优化。研究表明，RDCT-FEA综合方法可以有效预测模拟压水堆工况下PWSCC的起裂。

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引用次数: 0

From vulnerability to robustness: Radiation-hard isolation for BPR-enabled stacked nanosheet CFETs 从脆弱性到健壮性：bpr启用的堆叠纳米片cfet的抗辐射隔离

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

Nuclear Engineering and Technology

Pub Date : 2026-01-10 DOI: 10.1016/j.net.2025.104104

Dongwook Kim , Hanggyo Jung , Jimyeong Lee , Seungkyu Kim , Jongwook Jeon

The integration of Buried Power Rail (BPR) and Complementary FET (CFET) technologies is a promising way to improve power efficiency and circuit density in advanced logic devices. However, the radiation reliability of BPR-integrated logic and memory circuits remains insufficiently explored. For the first time, we provide a quantitative analysis of Single Event Effects (SEE) in BPR-integrated Si-CFET structures using semiconductor device- and circuit-level simulator. Simulation results show that the BPR structure increases the local electric field intensity by approximately 20.2 % compared to the conventional Front Power Rail (FPR), leading to extended charge collection paths and transient current densities up to 41.5 % higher under identical irradiation conditions. Moreover, mixed-mode simulations of SRAM latch circuits indicate that bit-flips can occur at Linear Energy Transfer (LET) levels as low as 1–2 MeV cm²/mg, indicating significant vulnerability under low-voltage operation. To address this, structural mitigation strategies—such as Buried Dielectric Isolation and Backside Contact—are proposed to increase the threshold LET margin to 34 MeV cm²/mg, representing a 17-fold improvement, without degrading device performance. These results offer critical design insights for enhancing radiation robustness in ultra-scaled logic and memory architectures using BPR integration.

埋地电源轨（BPR）和互补场效应管（CFET）技术的集成是提高先进逻辑器件功率效率和电路密度的一种很有前途的方法。然而，bpr集成逻辑和存储电路的辐射可靠性仍然没有得到充分的探索。本文首次利用半导体器件级和电路级模拟器对bpr集成Si-CFET结构中的单事件效应（SEE）进行了定量分析。仿真结果表明，与传统的前电源轨（FPR）相比，BPR结构的局部电场强度提高了约20.2%，在相同的辐照条件下，电荷收集路径延长，瞬态电流密度提高了41.5%。此外，SRAM锁存电路的混合模式模拟表明，在低至1-2 MeV cm2/mg的线性能量传递（LET）水平下，位翻转可能发生，表明在低压工作下存在明显的脆弱性。为了解决这一问题，研究人员提出了结构缓解策略，如埋藏介质隔离和背面接触，以将阈值LET裕度提高到34 MeV cm2/mg，在不降低器件性能的情况下，提高了17倍。这些结果为使用BPR集成来增强超大规模逻辑和存储架构的辐射鲁棒性提供了关键的设计见解。

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引用次数: 0

Development of an automated isotope identification algorithm based on second derivative and Bayesian statistics methods using medium energy resolution scintillation detectors 基于二阶导数和贝叶斯统计方法的中能量闪烁探测器同位素自动识别算法的开发

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

Nuclear Engineering and Technology

Pub Date : 2026-01-10 DOI: 10.1016/j.net.2026.104126

Haluk Yücel, Ege Can Karanfil, Bahadır Saygı

Radioisotope identification devices(RID) play a crucial role in detection and identification of illicit trafficking of radioactive/nuclear materials in nuclear security and nuclear safeguards. These devices utilize various algorithms for automated isotope identification(ID) without the need for expert intervention. In this study, an automated algorithm for real-time isotope identification is presented. The algorithm employs a second-derivative-based peak detection and a Bayesian-statistics-peak based ID approach. To demonstrate the suitability of the developed algorithm, it was applied to the gamma-ray spectra acquired with a medium energy -resolution LaBr₃(Ce) detector. In addition to point sources ⁶⁰Co, ¹⁰⁹Cd, ²²Na, ¹³⁷Cs, ²⁴¹Am, ¹⁵²Eu, and ¹³³Ba, the algorithm was also tested on the more complex gamma-ray spectra obtained from low enriched uranium reference materials 171 (EC-NRM171), and natural uranium and thorium minerals such as BL-2, BL-3, BL-4A, BL-5, RGU and OKA-2. To evaluate the performance of the algorithm, total scoring (ST) is calculated. For identification of ²²Na, ⁶⁰Co, and ¹³⁷Cs isotopes, the posterior probabilities were estimated to be greater than 99 %. For ¹³³Ba, ¹⁵²Eu, and ²⁴¹Am, the isotopes they were also correctly identified with higher posterior probabilities ranged from 92 % to 95 %. The developed algorithm successfully identified the isotopes contained in U-Th ore samples with a 100 % total score. Additionally, the performance evaluation of the results obtained with Certified Reference Uranium Materials also demonstrated 100 % score. For automatic ID, the photopeak-based Bayesian method, combined with the Mariscotti's peak detection method has great potential for real-time ID when implemented in RID devices.

放射性同位素识别装置在核安全和核保障中探测和识别非法贩运放射性/核材料方面发挥着至关重要的作用。这些设备利用各种算法进行自动同位素识别（ID），无需专家干预。在本研究中，提出了一种实时同位素识别的自动算法。该算法采用基于二阶导数的峰值检测和基于贝叶斯统计峰值的ID方法。为了证明所开发算法的适用性，将其应用于中能量分辨率LaBr3（Ce）探测器获得的伽马射线能谱。除了60Co、109Cd、22Na、137Cs、241Am、152Eu和133Ba点源外，该算法还对低浓缩铀参考物质171 （EC-NRM171）和天然铀钍矿物BL-2、BL-3、BL-4A、BL-5、RGU和OKA-2等更为复杂的伽马射线谱进行了测试。为了评估算法的性能，计算总得分（ST）。对于22Na、60Co和137Cs同位素的鉴定，估计后验概率大于99%。对于133Ba， 152Eu和241Am，他们也以较高的后验概率正确识别了同位素，其后验概率在92%到95%之间。该算法成功地鉴定了铀钍矿样品中所含的同位素，总得分为100%。此外，对认证参考铀材料所获得的结果的性能评价也达到了100%。对于自动ID，基于光峰的贝叶斯方法结合Mariscotti的峰值检测方法在RID设备中实现时具有很大的实时ID潜力。

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引用次数: 0

Cluster analysis of weekly 210Pb and 40K concentrations and cumulative meteorological effects in urban Spain (2006–2022) 2006-2022年西班牙城市周210Pb和40K浓度及累积气象效应聚类分析

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

Nuclear Engineering and Technology

Pub Date : 2026-01-09 DOI: 10.1016/j.net.2026.104128

Susana Petisco-Ferrero , Raquel Idoeta , Ander Nafarrate , Saroa Rozas , Jon Sáenz , Alain Ulazia , Gabriel Ibarra-Berastegui

This study analysed the weekly ²¹⁰Pb and ⁴⁰K concentrations from four Spanish laboratories located in urban areas recorded during the period of 2006–2022. The application of cluster analysis allowed the identification of two distinct clusters: one with lower values and the other with higher values. In the second stage, the wind and accumulated precipitation data were analysed for both clusters. The results indicated that accumulated precipitation was the main driving mechanism responsible for the observed weekly concentration patterns. The recorded precipitation in low-concentration clusters, was typically twice that of high-concentration weeks.

本研究分析了2006-2022年期间位于城市地区的四个西班牙实验室记录的每周210Pb和40K浓度。聚类分析的应用允许识别两个不同的集群：一个具有较低的值，另一个具有较高的值。在第二阶段，对两个星团的风和累积降水资料进行分析。结果表明，累积降水是周浓度变化的主要驱动机制。在低浓度集群中记录的降水量通常是高浓度周的两倍。

引用次数: 0

Degradation mechanism of oxide film on SIMP steel in LBE at temperatures above 550 °C 550℃以上LBE中SIMP钢氧化膜的降解机理

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

Nuclear Engineering and Technology

Pub Date : 2026-01-09 DOI: 10.1016/j.net.2026.104131

Tao Liu , Chongdou Yang , Xiangrong Fan , Di Yun , Wenguan Liu , Miroslav Popovic , Bingyao Zhao , Haiqing Xia , Zhongbo Liu , Jie Qiu

The corrosion behavior of SIMP steel in liquid lead-bismuth eutectic was investigated to elucidate the degradation mechanism of Fe-based protective oxide film in LBE when the temperature exceeds the critical threshold of 550 °C. Results show that a three-layer oxide film structure is formed on the surface of SIMP steel, consisting of an outer oxidation layer of Fe₃O₄, an inner oxidation layer of Fe-Cr spinel, and an internal oxidation zone. At 550 °C, SIMP steel forms a stable oxide layer and exhibits excellent resistance to LBE corrosion. However, at 600 °C, the increased diffusion coefficients of elements and their higher solubility in LBE accelerate elemental depletion, leading to the dissolution of the outer oxidation layer. The formation of a Cr₂O₃ band protects the matrix but also impedes elements diffusion from matrix to the oxides, promoting the formation of nanoscale voids and pores in the inner oxidation layer, resulting the failure of oxide film to resist lead-bismuth eutectic corrosion at 600 °C. The failure of the inner oxidation layer further accelerates the corrosion of the matrix.

研究了SIMP钢在铅铋共晶液中的腐蚀行为，阐明了当温度超过临界阈值550℃时，铁基氧化保护膜在LBE中的降解机理。结果表明：SIMP钢表面形成三层氧化膜结构，由外氧化层Fe3O4、内氧化层Fe-Cr尖晶石和内氧化区组成；在550℃时，SIMP钢形成稳定的氧化层，并表现出优异的抗LBE腐蚀性能。然而，在600℃时，元素扩散系数的增加和它们在LBE中的溶解度的提高加速了元素的耗竭，导致外层氧化层的溶解。Cr2O3带的形成保护了基体，但也阻碍了元素从基体向氧化物的扩散，促进了内部氧化层纳米级空洞和孔隙的形成，导致氧化膜在600℃下无法抵抗铅铋共晶腐蚀。内氧化层的破坏进一步加速了基体的腐蚀。

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引用次数: 0

Establishment of screening levels for thyroid contamination assessment in adults following a nuclear accident 核事故后成人甲状腺污染评估筛查水平的建立

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

Nuclear Engineering and Technology

Pub Date : 2026-01-07 DOI: 10.1016/j.net.2025.104103

Kihoon Kim, Seokwon Yoon, Hyungwoo Nam, Minsu Cho, Minseok Park

Rapid screening for thyroid contamination is crucial for implementing radiation protection measures in affected populations. Direct thyroid measurements using handheld radiation instruments are primarily performed during the early phases of a nuclear accident owing to their immediate results and operational convenience. This study aimed to derive dose conversion factors to convert measurements from handheld radiation instruments into thyroid equivalent doses. Thyroid screening levels were established for the South Korean Radiation Emergency Medical System. Instrument counting efficiencies were determined using a physical thyroid phantom and radioactive materials. Dose conversion factors were then derived by integrating the counting efficiencies with ¹³¹I retention functions and thyroid equivalent dose coefficients, under various intake scenarios. Screening levels were established using the derived conversion factors in conjunction with recommendations from the International Atomic Energy Agency, accounting for the time elapsed since radioiodine intake. The effectiveness of these levels was experimentally validated under various conditions, including detector performance, distance, and positioning. The derived screening levels can be used for offsite thyroid contamination measurements, facilitating rapid screening and dose assessment during radiation emergencies. Further studies are warranted to improve applicability in pediatric populations and reduce uncertainties in the current measurement system.

快速筛查甲状腺污染对于在受影响人群中实施辐射防护措施至关重要。使用手持式辐射仪器的直接甲状腺测量主要是在核事故的早期阶段进行的，因为它们的结果立即且操作方便。本研究旨在推导剂量转换因子，将手持式辐射仪器的测量值转换为甲状腺当量剂量。为韩国辐射紧急医疗系统制定了甲状腺筛查水平。仪器计数效率测定使用物理甲状腺幻影和放射性物质。然后，通过将计数效率与131I保留函数和甲状腺等效剂量系数进行积分，得出了不同摄入情景下的剂量转换因子。筛查水平是结合国际原子能机构的建议，根据摄入放射性碘后的时间计算得出的换算系数确定的。在各种条件下，包括探测器性能、距离和定位，实验验证了这些水平的有效性。导出的筛选水平可用于场外甲状腺污染测量，促进辐射紧急情况下的快速筛选和剂量评估。进一步的研究是必要的，以提高在儿科人群的适用性，并减少不确定性，目前的测量系统。

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引用次数: 0

Determination of 14C in radwaste samples through sequential wet oxidation and acid stripping extraction 序贯湿氧化-酸提法测定放射性废物样品中的14C

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

Nuclear Engineering and Technology

Pub Date : 2026-01-07 DOI: 10.1016/j.net.2026.104129

Feng-Yun J. Huang , Yi-Lun Chen , Tsuey-Lin Tsai , Chun-Yi Fang , Wan-Ling Chen , Ling-Ling Hsieh , Jiunn-Hsing Chao

¹⁴C is a long half-life nuclide (t_1/2 = 5730 y) produced naturally and artificially. It is a difficult-to-measure nuclide because of its pure beta decay, but identifying it is essential to ensuring appropriate radwaste disposal and management. This study developed and optimized a practical process for analyzing ¹⁴C from 21 radioactive waste samples. The measured activity of ¹⁴C in the radioactive waste samples ranged from 0.05 ± 0.04 to 68.83 ± 0.13 Bq g⁻¹, and their scaling factors (¹⁴C-to-⁶⁰Co activity ratio) were calculated to be 0.035–1.015. In summary, the developed simple and low-cost sequential wet-oxidation-acid-stripping extraction process can be routinely used for determining ¹⁴C in low-level radwaste samples in the laboratory.

14C是一种长半衰期的核素（t1/2 = 5730 y），自然和人工产生。由于其纯粹的β衰变，它是一种难以测量的核素，但识别它对于确保适当的放射性废物处理和管理至关重要。本研究开发并优化了从21个放射性废物样品中分析14C的实用过程。测得放射性废物样品中14C的活度范围为0.05±0.04 ~ 68.83±0.13 Bq g−1，其比例因子（14C / 60co活度比）为0.035 ~ 1.015。综上所述，所开发的简单、低成本的顺序湿式氧化-酸提萃取工艺可常规用于实验室低水平放射性废物样品中的14C测定。

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 : 2026-01-07 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