Nuclear Engineering and Technology最新文献_第5页

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 : 2026-05-01 Epub 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。

{"title":"Neutronic analysis of an EPR core employing PaO2 and NpO2 as burnable absorber coatings","authors":"S.M. Nymul Hasan Anik, Ali Mahdi, Saad Islam, Mohammad Monzur Hossain Khan, Swarna Sarker Toma","doi":"10.1016/j.net.2026.104151","DOIUrl":"10.1016/j.net.2026.104151","url":null,"abstract":"<div><div>This study investigates the use of Protactinium oxide (PaO<sub>2</sub>) and Neptunium oxide (NpO<sub>2</sub>) as regenerative burnable-absorber coatings for improving long-cycle reactivity control in a European Pressurized Reactor (EPR) fuel core. The proposed concept applies thin PaO<sub>2</sub> and NpO<sub>2</sub> layers to (Th-<sup>233</sup>U)O<sub>2</sub> Integral Fuel Burnable Absorber (IFBA) fuel rods and evaluates their neutronic performance relative to conventional UO<sub>2</sub>+Gd<sub>2</sub>O<sub>3</sub> and (Th-<sup>233</sup>U)O<sub>2</sub>+Gd<sub>2</sub>O<sub>3</sub> (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 <em>k</em><sub>eff</sub> than the Gd-bearing reference cores (because the coated designs are gadolinia-free), PaO<sub>2</sub>/NpO<sub>2</sub> 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 <sup>233</sup>U and <sup>239</sup>Pu. 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 PaO<sub>2</sub> and NpO<sub>2</sub> coatings offer a promising pathway for enhancing fuel-cycle economy, safety coefficients, and reactivity management in Generation III+ light-water-reactor cores.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104151"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146090483","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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 : 2026-05-01 Epub 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。

{"title":"Preliminary design and neutronic analyses of ECRH equatorial launcher toward CFEDR","authors":"Chao Xu , Ming Gao , Yuanyuan Kuang , Dingzhen Li , Chao Zhang , Hanlin Wang , Nengtao Zhou , Shanliang Zheng , Yunying Tang , Xiaojie Wang","doi":"10.1016/j.net.2026.104135","DOIUrl":"10.1016/j.net.2026.104135","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104135"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035725","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Preconditioned JFNK discontinuous Galerkin method for the SN neutron transport equation based on the WINGS framework 基于WINGS框架的SN中子输运方程的预条件JFNK不连续Galerkin方法

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

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-19 DOI: 10.1016/j.net.2026.104145

Xiantao Cui , Rong Zhou , Wei Zeng , Binbin Zhang , Shenglong Qiang , Di Xiang

This paper presents a solution scheme for the SN neutron transport equation using the discontinuous Galerkin method, implemented within the WINGS framework. The resulting SN-DG-WINGS program is capable of solving both steady-state eigenvalue problems and fixed-source problems, and incorporates the JFNK algorithm via the solver interface provided by WINGS. To improve computational efficiency, a preconditioned matrix construction method based on the A-matrix is introduced, along with a computational strategy for generating initial guesses. The accuracy of the program is verified through a series of benchmark cases, including one dimensional fixed source problems with anisotropic scattering and three dimensional criticality problems. Numerical results indicate an eigenvalue deviation within 200 pcm and a flux distribution error below 5 %. In terms of computational performance, the proposed preconditioning technique and initial guess strategy significantly improve convergence speed and stability. Large-scale parallel tests show that the program maintains a parallel efficiency of 47.3 % even at 1024 processors, demonstrating strong scalability.

本文提出了一种在WINGS框架下使用不连续伽辽金方法求解SN中子输运方程的方案。所得到的SN-DG-WINGS程序能够同时解决稳态特征值问题和固定源问题，并通过WINGS提供的求解器接口集成了JFNK算法。为了提高计算效率，提出了一种基于a矩阵的预条件矩阵构造方法，并提出了一种生成初始猜测的计算策略。通过一维各向异性散射固定源问题和三维临界问题等基准算例验证了程序的准确性。数值结果表明，本征值偏差在200pcm以内，磁通分布误差在5%以下。在计算性能方面，提出的预处理技术和初始猜测策略显著提高了收敛速度和稳定性。大规模并行测试表明，即使在1024个处理器的情况下，该程序仍保持47.3%的并行效率，显示出强大的可扩展性。

{"title":"Preconditioned JFNK discontinuous Galerkin method for the SN neutron transport equation based on the WINGS framework","authors":"Xiantao Cui , Rong Zhou , Wei Zeng , Binbin Zhang , Shenglong Qiang , Di Xiang","doi":"10.1016/j.net.2026.104145","DOIUrl":"10.1016/j.net.2026.104145","url":null,"abstract":"<div><div>This paper presents a solution scheme for the SN neutron transport equation using the discontinuous Galerkin method, implemented within the WINGS framework. The resulting SN-DG-WINGS program is capable of solving both steady-state eigenvalue problems and fixed-source problems, and incorporates the JFNK algorithm via the solver interface provided by WINGS. To improve computational efficiency, a preconditioned matrix construction method based on the A-matrix is introduced, along with a computational strategy for generating initial guesses. The accuracy of the program is verified through a series of benchmark cases, including one dimensional fixed source problems with anisotropic scattering and three dimensional criticality problems. Numerical results indicate an eigenvalue deviation within 200 pcm and a flux distribution error below 5 %. In terms of computational performance, the proposed preconditioning technique and initial guess strategy significantly improve convergence speed and stability. Large-scale parallel tests show that the program maintains a parallel efficiency of 47.3 % even at 1024 processors, demonstrating strong scalability.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104145"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035727","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Selective corrosion of δ-ferrite in austenitic stainless steel welds under wet–dry cycling: Influence of surface temperature for dry storage canister applications 干湿循环下奥氏体不锈钢焊缝δ-铁素体的选择性腐蚀：干燥储罐应用中表面温度的影响

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

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-13 DOI: 10.1016/j.net.2026.104141

Seunghyun Kim, Gidong Kim, Sang-Woo Song

This study investigates the effect of elevated surface temperature on chloride-induced stress corrosion cracking behavior in austenitic stainless steels welds exposed to MgCl₂-containing environments. U-bend specimens of 304L-ER308L and 316L-ER316L were subjected to controlled salt spray and heating conditions at 75 °C and 100 °C to simulate decay heat in dry storage systems. Despite the absence of visible surface moisture at elevated temperatures, extensive cracking was observed in 304L and ER308L, while ER316L exhibited no signs of crack initiation at 100 °C. SEM and EPMA analyses revealed selective crack propagation along δ-ferrite networks, with strong Cl and O enrichment detected inside the cracks, confirming the presence of aggressive localized chemistry. The susceptibility to CISCC was found to be closely related to the δ-ferrite composition: ER308L exhibited Ni-depleted, Cr-rich ferrite that facilitated anodic dissolution, whereas the δ-ferrite in ER316L was enriched in Ni and Mo, suppressing corrosion. The results demonstrate that microstructural and chemical factors, including alloying element distribution and salt hygroscopicity, play dominant roles in crack initiation and propagation under thermally accelerated conditions.

本研究探讨了表面温度升高对暴露于含mgcl2环境中的奥氏体不锈钢焊缝氯化物诱导应力腐蚀开裂行为的影响。304L-ER308L和316L-ER316L的u型试样分别在75°C和100°C的受控盐雾和加热条件下进行模拟干燥储存系统中的衰变热。尽管在高温下没有可见的表面水分，但在304L和ER308L中观察到广泛的裂纹，而ER316L在100°C时没有裂纹萌生的迹象。SEM和EPMA分析显示，裂纹沿δ-铁素体网络选择性扩展，裂纹内检测到强烈的Cl和O富集，证实了侵略性局部化学的存在。对CISCC的敏感性与δ-铁素体组成密切相关：ER308L中的δ-铁素体富含Ni和Mo，有利于阳极溶解，而ER316L中的δ-铁素体则富含Ni和Mo，抑制了腐蚀。结果表明，在热加速条件下，合金元素分布和盐的吸湿性等微观组织和化学因素对裂纹的萌生和扩展起主导作用。

{"title":"Selective corrosion of δ-ferrite in austenitic stainless steel welds under wet–dry cycling: Influence of surface temperature for dry storage canister applications","authors":"Seunghyun Kim, Gidong Kim, Sang-Woo Song","doi":"10.1016/j.net.2026.104141","DOIUrl":"10.1016/j.net.2026.104141","url":null,"abstract":"<div><div>This study investigates the effect of elevated surface temperature on chloride-induced stress corrosion cracking behavior in austenitic stainless steels welds exposed to MgCl<sub>2</sub>-containing environments. U-bend specimens of 304L-ER308L and 316L-ER316L were subjected to controlled salt spray and heating conditions at 75 °C and 100 °C to simulate decay heat in dry storage systems. Despite the absence of visible surface moisture at elevated temperatures, extensive cracking was observed in 304L and ER308L, while ER316L exhibited no signs of crack initiation at 100 °C. SEM and EPMA analyses revealed selective crack propagation along δ-ferrite networks, with strong Cl and O enrichment detected inside the cracks, confirming the presence of aggressive localized chemistry. The susceptibility to CISCC was found to be closely related to the δ-ferrite composition: ER308L exhibited Ni-depleted, Cr-rich ferrite that facilitated anodic dissolution, whereas the δ-ferrite in ER316L was enriched in Ni and Mo, suppressing corrosion. The results demonstrate that microstructural and chemical factors, including alloying element distribution and salt hygroscopicity, play dominant roles in crack initiation and propagation under thermally accelerated conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104141"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035813","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Pseudo-random pattern design and Monte Carlo evaluation of an active coded-aperture gamma-ray imager 有源编码孔径伽玛射线成像仪的伪随机图样设计与蒙特卡罗评价

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

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2025-12-29 DOI: 10.1016/j.net.2025.104109

Dukwoo Kim, Manhee Jeong

This study presents the development of an active coded-aperture gamma-ray imager based on pseudo-random patterns. Unlike conventional systems with mechanical collimators, the proposed design eliminates physical collimators by enabling the scintillator array to serve as the coding element. Pseudo-random patterns were optimized using the Great Deluge Algorithm to maximize a figure of merit incorporating cosine similarity, correlation, mean squared error, and peak-to-sidelobe ratio. The optimized patterns were implemented in a cylindrical GAGG(Ce) detector geometry, and responses were simulated using MCNPX-PoliMi. System matrices were constructed from omnidirectional photon incidence, and images were reconstructed with the maximum likelihood expectation maximization algorithm. Simulations demonstrated reliable reconstruction of single and multiple point sources as well as shaped sources. Angular resolution was measured as 5.436° vertically and 7.238° horizontally, comparable to the EPSILON-G system. Performance across 59.54–1836.07 keV achieved peak signal-to-noise ratio values above 30 dB and structural similarity index above 0.9. Although higher energies introduced more noise due to photon penetration and scattering, the results confirm the feasibility of lightweight, collimator-free, omnidirectional imaging suitable for unmanned platforms. Future work will focus on prototype fabrication and experimental validation.

本文介绍了一种基于伪随机模式的有源编码孔径伽玛射线成像仪的研制。与传统的机械准直器系统不同，该设计通过使闪烁体阵列作为编码元件来消除物理准直器。伪随机模式使用大洪水算法进行优化，以最大限度地利用余弦相似度、相关性、均方误差和峰旁瓣比。优化后的模式在圆柱形的GAGG（Ce）探测器几何结构中实现，并使用MCNPX-PoliMi对响应进行了模拟。利用全向光子入射构造系统矩阵，利用最大似然期望最大化算法重构图像。仿真结果表明，该方法可以可靠地重建单点源和多点源以及异形源。测量的角分辨率为垂直5.436°和水平7.238°，与EPSILON-G系统相当。在59.54-1836.07 keV范围内，峰值信噪比达到30 dB以上，结构相似指数达到0.9以上。尽管由于光子穿透和散射，更高的能量会带来更多的噪声，但结果证实了适用于无人平台的轻量化、无准直器、全向成像的可行性。未来的工作将集中在原型制造和实验验证上。

{"title":"Pseudo-random pattern design and Monte Carlo evaluation of an active coded-aperture gamma-ray imager","authors":"Dukwoo Kim, Manhee Jeong","doi":"10.1016/j.net.2025.104109","DOIUrl":"10.1016/j.net.2025.104109","url":null,"abstract":"<div><div>This study presents the development of an active coded-aperture gamma-ray imager based on pseudo-random patterns. Unlike conventional systems with mechanical collimators, the proposed design eliminates physical collimators by enabling the scintillator array to serve as the coding element. Pseudo-random patterns were optimized using the Great Deluge Algorithm to maximize a figure of merit incorporating cosine similarity, correlation, mean squared error, and peak-to-sidelobe ratio. The optimized patterns were implemented in a cylindrical GAGG(Ce) detector geometry, and responses were simulated using MCNPX-PoliMi. System matrices were constructed from omnidirectional photon incidence, and images were reconstructed with the maximum likelihood expectation maximization algorithm. Simulations demonstrated reliable reconstruction of single and multiple point sources as well as shaped sources. Angular resolution was measured as 5.436° vertically and 7.238° horizontally, comparable to the EPSILON-G system. Performance across 59.54–1836.07 keV achieved peak signal-to-noise ratio values above 30 dB and structural similarity index above 0.9. Although higher energies introduced more noise due to photon penetration and scattering, the results confirm the feasibility of lightweight, collimator-free, omnidirectional imaging suitable for unmanned platforms. Future work will focus on prototype fabrication and experimental validation.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104109"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980453","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Optimal control of reliability failure risk contagion dynamics in nuclear power systems 核电系统可靠性失效风险传染动力学的最优控制

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

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2025-12-26 DOI: 10.1016/j.net.2025.104108

Meirong Zhang , Jianyong Dai , Shangqing Gong , Jindao Huang

Risks originating from technology, management, and the external environment are a concern during the operation of nuclear power systems. The spread of these risks can impact the safe operation of nuclear power, especially when a component failure accelerates the risk impact, potentially leading to accidents and disasters. This paper develops a risk contagion dynamics model for nuclear power systems using epidemic dynamics mechanisms. The risk contagion coefficient due to reliability failure is utilized to adjust the reliability degradation equation. The SEIQRS model and Hamiltonian equation for nuclear power reliability risk contagion dynamics are reconstructed by introducing maintenance strategies like preventive maintenance, isolation maintenance, and defect maintenance. Optimal control methods are applied to mitigate the impact of reliability risk. Using a nuclear power plant operation system as an example shows how reliability failures amplify risks. Implementing maintenance strategies enhances reliability while reducing failures. Comparative analysis results underscore the effectiveness of addressing risk contagion impact through reliability degradation failure, thereby improving the reliability risk dynamic mechanism of nuclear power. The optimal maintenance strategy significantly boosts the reliability of nuclear power systems while mitigating the risk of contagion, providing valuable insights for optimal decision-making in nuclear power safety management.

在核电系统运行过程中，技术风险、管理风险和外部环境风险是一个值得关注的问题。这些风险的扩散会影响核电的安全运行，特别是当组件故障加速风险影响时，可能导致事故和灾难。利用流行动力学机制建立了核电系统风险传染动力学模型。利用可靠性失效的风险传染系数来调整可靠性退化方程。通过引入预防性维修、隔离维修和缺陷维修等维修策略，重构了核电可靠性风险传染动力学的SEIQRS模型和hamilton方程。采用最优控制方法减轻可靠性风险的影响。以某核电站运行系统为例，说明可靠性故障对风险的放大作用。实施维护策略可以提高可靠性，同时减少故障。对比分析结果强调了通过可靠性退化失效解决风险传染影响的有效性，从而完善核电可靠性风险动态机制。最优维护策略显著提高了核电系统的可靠性，同时降低了传染风险，为核电安全管理的最优决策提供了有价值的见解。

{"title":"Optimal control of reliability failure risk contagion dynamics in nuclear power systems","authors":"Meirong Zhang , Jianyong Dai , Shangqing Gong , Jindao Huang","doi":"10.1016/j.net.2025.104108","DOIUrl":"10.1016/j.net.2025.104108","url":null,"abstract":"<div><div>Risks originating from technology, management, and the external environment are a concern during the operation of nuclear power systems. The spread of these risks can impact the safe operation of nuclear power, especially when a component failure accelerates the risk impact, potentially leading to accidents and disasters. This paper develops a risk contagion dynamics model for nuclear power systems using epidemic dynamics mechanisms. The risk contagion coefficient due to reliability failure is utilized to adjust the reliability degradation equation. The SEIQRS model and Hamiltonian equation for nuclear power reliability risk contagion dynamics are reconstructed by introducing maintenance strategies like preventive maintenance, isolation maintenance, and defect maintenance. Optimal control methods are applied to mitigate the impact of reliability risk. Using a nuclear power plant operation system as an example shows how reliability failures amplify risks. Implementing maintenance strategies enhances reliability while reducing failures. Comparative analysis results underscore the effectiveness of addressing risk contagion impact through reliability degradation failure, thereby improving the reliability risk dynamic mechanism of nuclear power. The optimal maintenance strategy significantly boosts the reliability of nuclear power systems while mitigating the risk of contagion, providing valuable insights for optimal decision-making in nuclear power safety management.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104108"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980457","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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 : 2026-05-01 Epub 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%。

{"title":"Computational retrospective dosimetry with fortuitous dosimeters: An inter-laboratory comparison and evaluation of dose conversion coefficients","authors":"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","doi":"10.1016/j.net.2026.104152","DOIUrl":"10.1016/j.net.2026.104152","url":null,"abstract":"<div><div>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<sub>ge</sub>) and individual (DCC<sub>in</sub>) coefficients, and compared with simulated reference doses (WBD<sub>sim</sub>). DCC-derived WBDs showed overall improved agreement with WBD<sub>sim</sub> 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<sub>sim</sub> by up to a factor of 2.46, whereas WBD<sub>in</sub> (DCC<sub>in</sub>-derived WBD) and WBD<sub>ge</sub> (DCC<sub>ge</sub>-derived WBD) were improved to ranges of 0.75–1.36 and 1.57–2.17 times WBD<sub>sim</sub>, respectively. At the hip position under AP irradiation, mobile phone doses corresponded to only 25–36 % of WBD<sub>sim</sub>, while WBD<sub>in</sub> and WBD<sub>ge</sub> approached the reference values at 94–109 % and 71–102 %, respectively.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104152"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146090484","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Cyclic test and parametric analysis of steel shear wall made of two inclined slotted infill plates 两斜缝填充板钢剪力墙循环试验及参数分析

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

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-15 DOI: 10.1016/j.net.2026.104137

Mohammad Akram Faizy , Seyed Bahram Beheshti-Aval

This study investigates the seismic performance of a steel shear wall (SSW) made of two inclined slotted infill plates. Despite widespread use of SSWs, conventional steel shear walls (C-SSWs) face challenges such as limited energy dissipation and vulnerability to brittle failure under seismic loading. To overcome these issues, this research investigates the cyclic behavior of the slotted steel shear wall (S-SSW) compared to the conventional one. Understanding the impact of the configuration of infill plates is essential for improving seismic behavior and safety. The necessity of this research arises from the demand for enhanced ductility and energy absorption in seismic design. The methodological approach combines experimental testing of two 1/3-scale shear wall specimens to capture their hysteretic behavior. Alongside a parametric study utilizing Abaqus software is also used to evaluate the width-to-thickness ratios of the inclined strips over the behavior of the system. The findings reveal that while S-SSW exhibits reduced initial stiffness and strength, it demonstrates a substantially higher capacity for energy dissipation, contributing to improved seismic performance. Furthermore, the results of parametric studies reveal a clear dependence of both stiffness and strength on the width-to-thickness ratio of inclined strips.

本文研究了由两块斜缝填充板构成的钢剪力墙的抗震性能。尽管ssw被广泛使用，但传统的钢剪力墙（c - ssw）面临着诸如有限的能量耗散和地震荷载下脆性破坏等挑战。为了克服这些问题，本研究对开槽钢剪力墙（S-SSW）与常规剪力墙的循环性能进行了比较。了解填充板结构的影响对改善抗震性能和安全性至关重要。本研究的必要性来自于抗震设计中对增强延性和能量吸收的要求。该方法结合了两个1/3尺度剪力墙试件的实验测试，以捕捉其滞回行为。此外，还利用Abaqus软件进行参数化研究，以评估倾斜条带的宽度与厚度比对系统行为的影响。研究结果表明，虽然S-SSW的初始刚度和强度降低，但其能量耗散能力大大提高，有助于提高抗震性能。此外，参数化研究的结果表明，刚度和强度明显依赖于斜带的宽厚比。

{"title":"Cyclic test and parametric analysis of steel shear wall made of two inclined slotted infill plates","authors":"Mohammad Akram Faizy , Seyed Bahram Beheshti-Aval","doi":"10.1016/j.net.2026.104137","DOIUrl":"10.1016/j.net.2026.104137","url":null,"abstract":"<div><div>This study investigates the seismic performance of a steel shear wall (SSW) made of two inclined slotted infill plates. Despite widespread use of SSWs, conventional steel shear walls (C-SSWs) face challenges such as limited energy dissipation and vulnerability to brittle failure under seismic loading. To overcome these issues, this research investigates the cyclic behavior of the slotted steel shear wall (S-SSW) compared to the conventional one. Understanding the impact of the configuration of infill plates is essential for improving seismic behavior and safety. The necessity of this research arises from the demand for enhanced ductility and energy absorption in seismic design. The methodological approach combines experimental testing of two 1/3-scale shear wall specimens to capture their hysteretic behavior. Alongside a parametric study utilizing Abaqus software is also used to evaluate the width-to-thickness ratios of the inclined strips over the behavior of the system. The findings reveal that while S-SSW exhibits reduced initial stiffness and strength, it demonstrates a substantially higher capacity for energy dissipation, contributing to improved seismic performance. Furthermore, the results of parametric studies reveal a clear dependence of both stiffness and strength on the width-to-thickness ratio of inclined strips.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104137"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035722","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Determination of gadolinium by PGNAA with a D-T neutron generator and optimization algorithm 用D-T中子发生器和优化算法测定PGNAA中的钆

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

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-13 DOI: 10.1016/j.net.2026.104125

Can Cheng , Zhenhua Zhang , Jie Mei , Xiaorong Wang , Qing Shan , Pingkun Cai , Jiatong Li , Daqian Hei , Wenbao Jia

Soluble neutron poisons are introduced to maintain criticality safety for reprocessing spent nuclear fuel (SNF). Gd is a highly effective soluble neutron poison and has been widely applied in the process, thereby rendering online monitoring of Gd solution concentrations particularly important. In this study, a Gd solution measurement setup was developed using prompt gamma neutron activation analysis technology, comprising a D-T neutron generator and a BGO detector. Experimental results demonstrated that, due to the neutron self-shielding effect, the prompt gamma rays induced by Gd exhibited a nonlinear correlation with concentration, which was corrected using Monte Carlo simulations. The minimum detectable concentration (MDC) of Gd solution for the developed setup was 1.5 mg/L. Furthermore, an optimization algorithm–based method was proposed to determine the concentration of unknown samples without relying on neutron detectors to obtain the neutron self-shielding factor. Validation with two test samples confirmed the feasibility of this approach, showing a maximum deviation of 6.7 %. These results indicate that the developed setup and method are feasible for online monitoring of Gd solutions.

引入可溶性中子毒物来维持乏燃料后处理的临界安全。Gd是一种高效的可溶性中子毒，在生产过程中得到了广泛的应用，因此在线监测Gd溶液浓度就显得尤为重要。在本研究中，利用伽马中子激活分析技术开发了Gd溶液测量装置，该装置由一个D-T中子发生器和一个BGO探测器组成。实验结果表明，由于中子的自屏蔽效应，Gd诱导的提示伽马射线与浓度呈非线性相关，并通过蒙特卡罗模拟进行了修正。Gd溶液的最低检测浓度（MDC）为1.5 mg/L。在此基础上，提出了一种不依赖中子探测器获取中子自屏蔽系数的优化算法来确定未知样品浓度的方法。两个样品的验证证实了该方法的可行性，最大偏差为6.7%。这些结果表明，所建立的装置和方法对Gd溶液的在线监测是可行的。

{"title":"Determination of gadolinium by PGNAA with a D-T neutron generator and optimization algorithm","authors":"Can Cheng , Zhenhua Zhang , Jie Mei , Xiaorong Wang , Qing Shan , Pingkun Cai , Jiatong Li , Daqian Hei , Wenbao Jia","doi":"10.1016/j.net.2026.104125","DOIUrl":"10.1016/j.net.2026.104125","url":null,"abstract":"<div><div>Soluble neutron poisons are introduced to maintain criticality safety for reprocessing spent nuclear fuel (SNF). Gd is a highly effective soluble neutron poison and has been widely applied in the process, thereby rendering online monitoring of Gd solution concentrations particularly important. In this study, a Gd solution measurement setup was developed using prompt gamma neutron activation analysis technology, comprising a D-T neutron generator and a BGO detector. Experimental results demonstrated that, due to the neutron self-shielding effect, the prompt gamma rays induced by Gd exhibited a nonlinear correlation with concentration, which was corrected using Monte Carlo simulations. The minimum detectable concentration (MDC) of Gd solution for the developed setup was 1.5 mg/L. Furthermore, an optimization algorithm–based method was proposed to determine the concentration of unknown samples without relying on neutron detectors to obtain the neutron self-shielding factor. Validation with two test samples confirmed the feasibility of this approach, showing a maximum deviation of 6.7 %. These results indicate that the developed setup and method are feasible for online monitoring of Gd solutions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104125"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980451","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

STPA-based approach to identifying extraneous errors of commission in FOAK advanced reactors 基于stpa的FOAK先进反应堆外部调试误差识别方法

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

Nuclear Engineering and Technology

Pub Date : 2026-05-01 Epub Date: 2026-01-07 DOI: 10.1016/j.net.2026.104130

Sung-Min Shin, Yochan Kim, Jinkyun Park, Jin Hee Park

First-of-a-kind (FOAK) advanced nuclear reactors, including small modular reactors, increasingly rely on autonomous safety systems to achieve high levels of safety and efficiency. While such designs reduce the need for manual intervention, they also introduce new complexities in supervisory control that may lead to errors of commission (EOCs). In particular, extraneous EOCs, referring to operator actions that are unnecessary and potentially hazardous, have not been systematically addressed by conventional human reliability analysis methods. This study investigates the feasibility of applying Systems-Theoretic Process Analysis (STPA) to systematically identify extraneous EOCs in autonomous safety contexts. An application to a fail-safe passive safety system demonstrates how STPA can trace the causal mechanisms of inappropriate operator interventions, revealing loss scenarios and pathways specific to extraneous EOCs. Beyond this methodological validation, the study derives example requirements to support safe interaction between autonomous safety functions and human operators. These requirements illustrate how STPA results can be translated into general guidance for ensuring that human–automation interactions preserve system safety while accommodating supervisory flexibility. In doing so, the proposed approach extends the analytical scope of human reliability methods and provides a structured foundation for managing operator–system dynamics in FOAK advanced reactors.

包括小型模块化反应堆在内的首个先进核反应堆越来越依赖自主安全系统来实现高水平的安全性和效率。虽然这种设计减少了人工干预的需要，但它们也在监督控制中引入了新的复杂性，可能导致操作错误（eoc）。特别是，对于不必要的、潜在危险的操作，常规的人为可靠性分析方法还没有系统地解决。本研究探讨了应用系统理论过程分析（STPA）系统识别自主安全环境中外部eoc的可行性。故障安全被动安全系统的应用表明，STPA可以追踪操作人员不当干预的因果机制，揭示外部EOCs特有的损失情景和路径。除了这种方法验证之外，该研究还派生了支持自主安全功能与人类操作员之间安全交互的示例要求。这些要求说明了如何将STPA结果转化为一般指导，以确保人机交互在适应监管灵活性的同时保持系统安全。在此过程中，所提出的方法扩展了人类可靠性方法的分析范围，并为管理FOAK先进反应堆的操作系统动力学提供了结构化基础。

{"title":"STPA-based approach to identifying extraneous errors of commission in FOAK advanced reactors","authors":"Sung-Min Shin, Yochan Kim, Jinkyun Park, Jin Hee Park","doi":"10.1016/j.net.2026.104130","DOIUrl":"10.1016/j.net.2026.104130","url":null,"abstract":"<div><div>First-of-a-kind (FOAK) advanced nuclear reactors, including small modular reactors, increasingly rely on autonomous safety systems to achieve high levels of safety and efficiency. While such designs reduce the need for manual intervention, they also introduce new complexities in supervisory control that may lead to errors of commission (EOCs). In particular, extraneous EOCs, referring to operator actions that are unnecessary and potentially hazardous, have not been systematically addressed by conventional human reliability analysis methods. This study investigates the feasibility of applying Systems-Theoretic Process Analysis (STPA) to systematically identify extraneous EOCs in autonomous safety contexts. An application to a fail-safe passive safety system demonstrates how STPA can trace the causal mechanisms of inappropriate operator interventions, revealing loss scenarios and pathways specific to extraneous EOCs. Beyond this methodological validation, the study derives example requirements to support safe interaction between autonomous safety functions and human operators. These requirements illustrate how STPA results can be translated into general guidance for ensuring that human–automation interactions preserve system safety while accommodating supervisory flexibility. In doing so, the proposed approach extends the analytical scope of human reliability methods and provides a structured foundation for managing operator–system dynamics in FOAK advanced reactors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104130"},"PeriodicalIF":2.6,"publicationDate":"2026-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980456","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0