Pub Date : 2025-12-15DOI: 10.1016/j.net.2025.104085
Yahya Sadeghi
Optimizing tokamak operation requires a precise understanding of magnetohydrodynamic equilibrium. This paper presents a numerical study of plasma shape, displacement, poloidal beta (), and internal inductance () in the Alvand-U tokamak. The analysis is performed using a newly developed computational code that efficiently solves the nonlinear Grad–Shafranov equation with advanced iterative methods. Two distinct source term models are employed: a simplified current density profile to investigate plasma shape and displacement, and a combined current–pressure profile to compute and . For both models, we quantify the effects of varying the plasma current and the vertical field current. In all cases, the plasma boundary is defined by the limiter contact point, with current density set to zero outside this boundary. The results clearly demonstrate the dependence of these equilibrium parameters on the operational currents, providing critical insight for optimizing the performance of the Alvand-U tokamak.
{"title":"Investigation of plasma shape, displacement, poloidal beta, and internal inductance in the Alvand-U tokamak through the solution of the Grad–Shafranov equation","authors":"Yahya Sadeghi","doi":"10.1016/j.net.2025.104085","DOIUrl":"10.1016/j.net.2025.104085","url":null,"abstract":"<div><div>Optimizing tokamak operation requires a precise understanding of magnetohydrodynamic equilibrium. This paper presents a numerical study of plasma shape, displacement, poloidal beta (<span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span>), and internal inductance (<span><math><msub><mrow><mi>ℓ</mi></mrow><mrow><mi>i</mi></mrow></msub></math></span>) in the Alvand-U tokamak. The analysis is performed using a newly developed computational code that efficiently solves the nonlinear Grad–Shafranov equation with advanced iterative methods. Two distinct source term models are employed: a simplified current density profile to investigate plasma shape and displacement, and a combined current–pressure profile to compute <span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span> and <span><math><msub><mrow><mi>ℓ</mi></mrow><mrow><mi>i</mi></mrow></msub></math></span>. For both models, we quantify the effects of varying the plasma current and the vertical field current. In all cases, the plasma boundary is defined by the limiter contact point, with current density set to zero outside this boundary. The results clearly demonstrate the dependence of these equilibrium parameters on the operational currents, providing critical insight for optimizing the performance of the Alvand-U tokamak.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104085"},"PeriodicalIF":2.6,"publicationDate":"2025-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145977205","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}
Pub Date : 2025-12-15DOI: 10.1016/j.net.2025.104086
Zeyi Dai , Jia Li , Pengwei Huang , Chaofan An , Yongjin Ding , Dengshi Shi , Hongwei Yue , Yuxin Zhang , Xinwu Yu , Xuyang Qiao , Lianmin Zheng , Yuancun Nie
The Wuhan Advanced Light Source (WALS) is a high-brightness fourth-generation synchrotron radiation light source designed to generate high-quality X-ray beams using a top-up linear accelerator (LINAC) as an injector. The LINAC will provide electron beams for a low-energy storage ring (1.5 GeV), a medium-energy storage ring (4 GeV), and a free-electron laser (FEL). In the first phase, a low-energy diffraction-limited storage ring (DLSR) operating at 1.5 GeV is proposed. To meet the high current requirements for the DLSR and low beam emittance for the FEL, a photoinjector-based top-up LINAC is identified as the optimal solution. This study employs a multi-objective optimization algorithm to improve the photoinjector's performance and uses a laser pulse delay scheme validated on the TTX platform at Tsinghua University to achieve a pulse train structure with a single bunch charge of 1 nC and a time gap between micro-bunches of 2.1 ns. Beam optimization simulations for the 1.5 GeV LINAC at a bunch charge of 1 nC yield an RMS energy spread below 0.1 %, and normalized emittances of 1.64 mm·mrad (horizontal) and 0.97 mm·mrad (vertical). These results demonstrate the feasibility of the LINAC system to simultaneously provide high-quality beams for both the DLSRs and the FELs.
{"title":"Physical design of the 1.5 GeV LINAC injector for the WALS facility","authors":"Zeyi Dai , Jia Li , Pengwei Huang , Chaofan An , Yongjin Ding , Dengshi Shi , Hongwei Yue , Yuxin Zhang , Xinwu Yu , Xuyang Qiao , Lianmin Zheng , Yuancun Nie","doi":"10.1016/j.net.2025.104086","DOIUrl":"10.1016/j.net.2025.104086","url":null,"abstract":"<div><div>The Wuhan Advanced Light Source (WALS) is a high-brightness fourth-generation synchrotron radiation light source designed to generate high-quality X-ray beams using a top-up linear accelerator (LINAC) as an injector. The LINAC will provide electron beams for a low-energy storage ring (1.5 GeV), a medium-energy storage ring (4 GeV), and a free-electron laser (FEL). In the first phase, a low-energy diffraction-limited storage ring (DLSR) operating at 1.5 GeV is proposed. To meet the high current requirements for the DLSR and low beam emittance for the FEL, a photoinjector-based top-up LINAC is identified as the optimal solution. This study employs a multi-objective optimization algorithm to improve the photoinjector's performance and uses a laser pulse delay scheme validated on the TTX platform at Tsinghua University to achieve a pulse train structure with a single bunch charge of 1 nC and a time gap between micro-bunches of 2.1 ns. Beam optimization simulations for the 1.5 GeV LINAC at a bunch charge of 1 nC yield an RMS energy spread below 0.1 %, and normalized emittances of 1.64 mm·mrad (horizontal) and 0.97 mm·mrad (vertical). These results demonstrate the feasibility of the LINAC system to simultaneously provide high-quality beams for both the DLSRs and the FELs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104086"},"PeriodicalIF":2.6,"publicationDate":"2025-12-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787950","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}
Deep-penetration radiation shielding problems present a significant computational challenge for the standard Monte Carlo (MC) method due to statistical inefficiency in low-flux regions. As a robust alternative, this study investigates The Random Ray Method (TRRM), which is founded on deterministic transport along randomly and uniformly sampled rays. A rigorous comparison between TRRM and the Multigroup Monte Carlo (MGMC) method was conducted by implementing both within a unified computational framework. Performance was assessed using two challenging shielding benchmarks—the three-dimensional Wagner model with thick shielding and a two-dimensional shielding facility with multi-bend maze—under four physics configurations that combines multigroup (47-group) and one-group energy treatments with isotropic and anisotropic scattering. The results show that while both methods agree in high-flux regions, MGMC performance degrades significantly as normalized flux has attenuated by 6–7 orders of magnitude, whereas TRRM remains statistically robust. Consequently, TRRM is several orders of magnitude more efficient in these deep-penetration regions, with its Figure of Merit (FOM) exceeding MGMC's by factors of over 104. Critically, the study reveals that the computational advantage of TRRM is substantially amplified in the most physically realistic scenarios (multigroup with anisotropic scattering). Although these complexities increase TRRM's per-ray computational cost, the significant variance reduction from its global sampling strategy overwhelmingly compensates for it. These findings establish TRRM as a highly efficient deterministic alternative for high-fidelity shielding analyses.
{"title":"The random ray method for challenging deep-penetration shielding problems: A rigorous comparison with multigroup Monte Carlo","authors":"Shuai Qin, Jiacheng Li, Shihong Li, Xiangchun Tian, Qian Zhang","doi":"10.1016/j.net.2025.104083","DOIUrl":"10.1016/j.net.2025.104083","url":null,"abstract":"<div><div>Deep-penetration radiation shielding problems present a significant computational challenge for the standard Monte Carlo (MC) method due to statistical inefficiency in low-flux regions. As a robust alternative, this study investigates The Random Ray Method (TRRM), which is founded on deterministic transport along randomly and uniformly sampled rays. A rigorous comparison between TRRM and the Multigroup Monte Carlo (MGMC) method was conducted by implementing both within a unified computational framework. Performance was assessed using two challenging shielding benchmarks—the three-dimensional Wagner model with thick shielding and a two-dimensional shielding facility with multi-bend maze—under four physics configurations that combines multigroup (47-group) and one-group energy treatments with isotropic and anisotropic scattering. The results show that while both methods agree in high-flux regions, MGMC performance degrades significantly as normalized flux has attenuated by 6–7 orders of magnitude, whereas TRRM remains statistically robust. Consequently, TRRM is several orders of magnitude more efficient in these deep-penetration regions, with its Figure of Merit (FOM) exceeding MGMC's by factors of over 10<sup>4</sup>. Critically, the study reveals that the computational advantage of TRRM is substantially amplified in the most physically realistic scenarios (multigroup with anisotropic scattering). Although these complexities increase TRRM's per-ray computational cost, the significant variance reduction from its global sampling strategy overwhelmingly compensates for it. These findings establish TRRM as a highly efficient deterministic alternative for high-fidelity shielding analyses.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104083"},"PeriodicalIF":2.6,"publicationDate":"2025-12-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787537","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}
Pub Date : 2025-12-13DOI: 10.1016/j.net.2025.104082
Peng Yu , Qianhong Huang , Xinlin Wang , Yijun Zhong , Qingyi Tan , Jun Wang , Zhe Wang , Zhanhui Wang
The control of safety factor profile helps to reduce turbulent transport and improve core confinement. Based on HL-3 device parameters, this study employs METIS to investigate control laws of safety factor profile through adjustments of ECW power peak deposition position, deposition width, ramp-up rate, ramp-up time, and plasma effective charge number, while analyzing their impacts on core confinement performance in hybrid scenarios. By appropriately adjusting the power deposition position and width of ECW, as well as regulating its power ramp-up time, safety factor profile can be maintained with characteristics of zero magnetic shear hybrid scenario. At the same time, transport barrier will form in the dynamic profiles, the transport coefficient will reduce, plasma parameters and core confinement will improve significantly. Moreover, the effect of ECW on the improvement of core confinement in the plasma current ramp-up phase is studied.
{"title":"Integrated modeling of improving core confinement with ECW based on HL-3 hybrid scenario","authors":"Peng Yu , Qianhong Huang , Xinlin Wang , Yijun Zhong , Qingyi Tan , Jun Wang , Zhe Wang , Zhanhui Wang","doi":"10.1016/j.net.2025.104082","DOIUrl":"10.1016/j.net.2025.104082","url":null,"abstract":"<div><div>The control of safety factor profile helps to reduce turbulent transport and improve core confinement. Based on HL-3 device parameters, this study employs METIS to investigate control laws of safety factor profile through adjustments of ECW power peak deposition position, deposition width, ramp-up rate, ramp-up time, and plasma effective charge number, while analyzing their impacts on core confinement performance in hybrid scenarios. By appropriately adjusting the power deposition position and width of ECW, as well as regulating its power ramp-up time, safety factor profile can be maintained with characteristics of zero magnetic shear hybrid scenario. At the same time, transport barrier will form in the dynamic profiles, the transport coefficient will reduce, plasma parameters and core confinement will improve significantly. Moreover, the effect of ECW on the improvement of core confinement in the plasma current ramp-up phase is studied.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104082"},"PeriodicalIF":2.6,"publicationDate":"2025-12-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787949","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}
Pub Date : 2025-12-12DOI: 10.1016/j.net.2025.104079
Semra Daydas, Ali Tiftikci
This study investigates the feasibility of using a Uranium–Manganese (U–Mn) alloy as an alternative fuel for the Dual Fluid Reactor (DFRm) concept to increase the temperature margin, along with a Magnesium Oxide–Beryllium Oxide (MgO–BeO) ceramic fuel tube. Neutronic analyses were performed using the SERPENT 1.1.7 Monte Carlo code with the ENDF/B-VII cross-section library to evaluate fuel performance, reactivity behavior, and safety margins. The results indicate that the U–Mn fuel exhibits lower values and shorter fuel cycle length to those of the U–Cr fuel, while providing the advantage of a lower eutectic temperature. Reactivity coefficients found to be negative for both fuel and coolant with the SiC fuel tube, ensuring inherent safety during temperature excursions. However, for the MgO–BeO configuration, the reactivity coefficients for MgO-BeO were found to be positive, which represents a critical drawback of this material; hence, further geometrical optimization is required. Consequently, although U–Mn fuel maintains negative temperature feedback under SiC-based configurations, alternative tube materials such as MgO–BeO require further optimization to ensure stable and inherently safe reactivity behavior throughout the fuel cycle. Future research could focus on optimizing reactor geometry to enhance the utilization potential of U–Mn fuel.
本研究探讨了使用铀-锰（U-Mn）合金作为双流体反应堆（DFRm）概念的替代燃料的可行性，以提高温度裕度，同时使用氧化镁-氧化铍（MgO-BeO）陶瓷燃料管。中子分析使用SERPENT 1.1.7 Monte Carlo代码和ENDF/B-VII截面库进行，以评估燃料性能、反应性行为和安全裕度。结果表明，与U-Cr燃料相比，U-Mn燃料具有更低的keff值和更短的燃料循环长度，同时具有更低的共晶温度。使用碳化硅燃料管的燃料和冷却剂的反应性系数均为负，确保了温度漂移时的固有安全性。然而，对于MgO-BeO结构，MgO-BeO的反应性系数被发现是正的，这代表了这种材料的一个关键缺点；因此，需要进一步的几何优化。因此，尽管U-Mn燃料在基于sic的配置下保持负温度反馈，但替代管材料（如MgO-BeO）需要进一步优化，以确保整个燃料循环过程中稳定和固有安全的反应性行为。未来的研究重点应放在优化反应堆结构上，以提高铀锰燃料的利用潜力。
{"title":"Neutronic performance analysis of U–Mn fuel and MgO-BeO tube material in the dual fluid reactor","authors":"Semra Daydas, Ali Tiftikci","doi":"10.1016/j.net.2025.104079","DOIUrl":"10.1016/j.net.2025.104079","url":null,"abstract":"<div><div>This study investigates the feasibility of using a Uranium–Manganese (U–Mn) alloy as an alternative fuel for the Dual Fluid Reactor (DFR<sub>m</sub>) concept to increase the temperature margin, along with a Magnesium Oxide–Beryllium Oxide (MgO–BeO) ceramic fuel tube. Neutronic analyses were performed using the SERPENT 1.1.7 Monte Carlo code with the ENDF/B-VII cross-section library to evaluate fuel performance, reactivity behavior, and safety margins. The results indicate that the U–Mn fuel exhibits lower <span><math><mrow><msub><mi>k</mi><mrow><mi>e</mi><mi>f</mi><mi>f</mi></mrow></msub></mrow></math></span> values and shorter fuel cycle length to those of the U–Cr fuel, while providing the advantage of a lower eutectic temperature. Reactivity coefficients found to be negative for both fuel and coolant with the SiC fuel tube, ensuring inherent safety during temperature excursions. However, for the MgO–BeO configuration, the reactivity coefficients for MgO-BeO were found to be positive, which represents a critical drawback of this material; hence, further geometrical optimization is required. Consequently, although U–Mn fuel maintains negative temperature feedback under SiC-based configurations, alternative tube materials such as MgO–BeO require further optimization to ensure stable and inherently safe reactivity behavior throughout the fuel cycle. Future research could focus on optimizing reactor geometry to enhance the utilization potential of U–Mn fuel.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104079"},"PeriodicalIF":2.6,"publicationDate":"2025-12-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787530","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}
Pub Date : 2025-12-12DOI: 10.1016/j.net.2025.104073
Shan Liao , Li Yang , Jing Zhang , Sangang Li , Yi Cheng
Deep low-dose CT (LDCT) reconstruction methods commonly face the spectral bias problem. Where at the aspect of parameter updating, the gradients of low-frequency components tend to dominate the optimization process, thereby impeding the effective backpropagation of high-frequency component gradients. Regarding this problem, we propose a novel Cross-Network Semantic Transfer (CNST) framework. In the framework, to prevent the obstruction of low-frequency to high-frequency, the parameter updates of low-frequency and high-frequency components is decoupled into two separate backpropagation processes. Then, module-based frequency feature encoding is employed to construct a constraint loss, thereby enabling the integration of high and low frequency semantic information. In addition, for low-frequency encoding, to reduce the parameters involved in semantic a novel re-parameterization block is introduced. For high-frequency encoding, to compensate for the insufficient ability of data fidelity item in preserving high-frequency textures, based on attention encoding, an extra high-frequency loss are introduced. And both the high-frequency and low-frequency modules are trained within a generative adversarial framework. Experimental results demonstrate that CNST achieves competitive performance compared with some state-of-the-art methods. While effectively mitigating the spectral bias problem, CNST reconstructs textures closest to the real full-dose CT image.
{"title":"CNST: Cross-Network Semantic Transfer for low-dose CT denoising with attention encoding","authors":"Shan Liao , Li Yang , Jing Zhang , Sangang Li , Yi Cheng","doi":"10.1016/j.net.2025.104073","DOIUrl":"10.1016/j.net.2025.104073","url":null,"abstract":"<div><div>Deep low-dose CT (LDCT) reconstruction methods commonly face the spectral bias problem. Where at the aspect of parameter updating, the gradients of low-frequency components tend to dominate the optimization process, thereby impeding the effective backpropagation of high-frequency component gradients. Regarding this problem, we propose a novel Cross-Network Semantic Transfer (CNST) framework. In the framework, to prevent the obstruction of low-frequency to high-frequency, the parameter updates of low-frequency and high-frequency components is decoupled into two separate backpropagation processes. Then, module-based frequency feature encoding is employed to construct a constraint loss, thereby enabling the integration of high and low frequency semantic information. In addition, for low-frequency encoding, to reduce the parameters involved in semantic a novel re-parameterization block is introduced. For high-frequency encoding, to compensate for the insufficient ability of data fidelity item in preserving high-frequency textures, based on attention encoding, an extra high-frequency loss are introduced. And both the high-frequency and low-frequency modules are trained within a generative adversarial framework. Experimental results demonstrate that CNST achieves competitive performance compared with some state-of-the-art methods. While effectively mitigating the spectral bias problem, CNST reconstructs textures closest to the real full-dose CT image.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104073"},"PeriodicalIF":2.6,"publicationDate":"2025-12-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145840856","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}
Pub Date : 2025-12-11DOI: 10.1016/j.net.2025.104081
Wonseok Yang , Joonsoo Ock , Kwangseo Kim , Samuel Park , Nakkyu Chae , Haewoong Kim , Kwangsoo Park , Min-Ho Lee , Sungyeol Choi
The decommissioning of nuclear power plants presents significant challenges due to the release of radioactive aerosols from contaminated or activated metal cutting, posing risks of internal radiation exposure. To protect workers, it is crucial to characterize aerosol generation and verify the performance of air purification systems. Although previous studies relied on lab-scale experiments, full-scale mock-up testing is necessary to validate under field conditions. This study conducted remote oxy-fuel cutting experiments on a mock-up reactor pressure vessel (RPV) to evaluate aerosol characteristics and filtration efficiency. The mock-up, simulating the upper shell of the Kori Unit 1 RPV, was enclosed within a shielding tent connected to a ventilation system. During thermal cutting, we confirmed a bimodal size distribution, with nanoparticles (<100 nm) comprising a significant fraction. Chemical analysis identified that aerosol contained the key elements of RPV materials such as iron, chromium, nickel, and manganese. Filtration efficiency of mock-up system exceeded 99.87 % for particles under 10 μm. However, the dose conversion factors for inhalation calculated from experimental data were up to 4.71 times higher than the ICRP-recommended values. These findings emphasize the importance of precise aerosol monitoring and respiratory protective equipment to enhance safety protocols in nuclear decommissioning.
{"title":"Nano-to-micro aerosol contaminants emissions from dismantling of nuclear reactor pressure vessel using mock-up experiments","authors":"Wonseok Yang , Joonsoo Ock , Kwangseo Kim , Samuel Park , Nakkyu Chae , Haewoong Kim , Kwangsoo Park , Min-Ho Lee , Sungyeol Choi","doi":"10.1016/j.net.2025.104081","DOIUrl":"10.1016/j.net.2025.104081","url":null,"abstract":"<div><div>The decommissioning of nuclear power plants presents significant challenges due to the release of radioactive aerosols from contaminated or activated metal cutting, posing risks of internal radiation exposure. To protect workers, it is crucial to characterize aerosol generation and verify the performance of air purification systems. Although previous studies relied on lab-scale experiments, full-scale mock-up testing is necessary to validate under field conditions. This study conducted remote oxy-fuel cutting experiments on a mock-up reactor pressure vessel (RPV) to evaluate aerosol characteristics and filtration efficiency. The mock-up, simulating the upper shell of the Kori Unit 1 RPV, was enclosed within a shielding tent connected to a ventilation system. During thermal cutting, we confirmed a bimodal size distribution, with nanoparticles (<100 nm) comprising a significant fraction. Chemical analysis identified that aerosol contained the key elements of RPV materials such as iron, chromium, nickel, and manganese. Filtration efficiency of mock-up system exceeded 99.87 % for particles under 10 μm. However, the dose conversion factors for inhalation calculated from experimental data were up to 4.71 times higher than the ICRP-recommended values. These findings emphasize the importance of precise aerosol monitoring and respiratory protective equipment to enhance safety protocols in nuclear decommissioning.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104081"},"PeriodicalIF":2.6,"publicationDate":"2025-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787954","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}
Pub Date : 2025-12-11DOI: 10.1016/j.net.2025.104078
Yujin Eom , Geon Shin , Heehun Yang , Soyeon Choi , Hyeongseok Eun , Joon-Ku Lee , Hoyoung Yoo
This paper proposes a GPU-based high-speed signal generation algorithm for effectively simulating the operational environment of the Ex-Core Neutron Flux Monitoring System (ENFMS), which is essential for advanced reactor systems such as Small Modular Reactors (SMRs). Accurate and rapid modeling of neutron, gamma-ray, and electrical noise signals is essential for reliable nuclear fuel monitoring and early anomaly detection. Although conventional CPU-based sequential simulation methods provide precise results, they become impractical under high reactor power conditions or extended simulation durations due to excessive computational demands. To resolve these limitations, we developed a parallel computing framework optimized for high-performance task distribution between CPU and GPU resources. Experimental results demonstrate that the proposed GPU-based implementation reduces elapsed times by up to 99.57 %, 99.43 %, and 98.54 % compared to CPU implementations using MATLAB, Python, and C, respectively. Therefore, the proposed GPU-based parallel algorithm significantly enhances feasibility of realistic and efficient ENFMS simulations, contributing to accelerated development and validation of digital and compact SMR systems.
{"title":"GPU-based high-speed reactor signal generator for Ex-core neutron flux monitoring system validation","authors":"Yujin Eom , Geon Shin , Heehun Yang , Soyeon Choi , Hyeongseok Eun , Joon-Ku Lee , Hoyoung Yoo","doi":"10.1016/j.net.2025.104078","DOIUrl":"10.1016/j.net.2025.104078","url":null,"abstract":"<div><div>This paper proposes a GPU-based high-speed signal generation algorithm for effectively simulating the operational environment of the Ex-Core Neutron Flux Monitoring System (ENFMS), which is essential for advanced reactor systems such as Small Modular Reactors (SMRs). Accurate and rapid modeling of neutron, gamma-ray, and electrical noise signals is essential for reliable nuclear fuel monitoring and early anomaly detection. Although conventional CPU-based sequential simulation methods provide precise results, they become impractical under high reactor power conditions or extended simulation durations due to excessive computational demands. To resolve these limitations, we developed a parallel computing framework optimized for high-performance task distribution between CPU and GPU resources. Experimental results demonstrate that the proposed GPU-based implementation reduces elapsed times by up to 99.57 %, 99.43 %, and 98.54 % compared to CPU implementations using MATLAB, Python, and C, respectively. Therefore, the proposed GPU-based parallel algorithm significantly enhances feasibility of realistic and efficient ENFMS simulations, contributing to accelerated development and validation of digital and compact SMR systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104078"},"PeriodicalIF":2.6,"publicationDate":"2025-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787952","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}
Pub Date : 2025-12-11DOI: 10.1016/j.net.2025.104080
Shuaike Lv , Changsheng Dai , Dongdong Hu , Tiancheng Zhong , Weifeng Wu , Xinjian Wang
Muon tomography is a promising technique for the detection and imaging of high-Z materials. A detector with excellent timing and spatial resolution can significantly improve imaging accuracy. In this study, we propose a scintillation detector design based on a SiPM array readout and conduct detailed simulations to investigate its timing and spatial performances. Preliminary results indicate that the detector can achieve a time resolution better than 30 ps and a spatial resolution of approximately 1.5 mm. This design offers a compact, single-detector solution with high performance, which has great potential to simplify muon scattering tomography systems and further enhance image effect.
{"title":"Simulation of a time and spatial sensitive plastic scintillator detector","authors":"Shuaike Lv , Changsheng Dai , Dongdong Hu , Tiancheng Zhong , Weifeng Wu , Xinjian Wang","doi":"10.1016/j.net.2025.104080","DOIUrl":"10.1016/j.net.2025.104080","url":null,"abstract":"<div><div>Muon tomography is a promising technique for the detection and imaging of high-Z materials. A detector with excellent timing and spatial resolution can significantly improve imaging accuracy. In this study, we propose a scintillation detector design based on a SiPM array readout and conduct detailed simulations to investigate its timing and spatial performances. Preliminary results indicate that the detector can achieve a time resolution better than 30 ps and a spatial resolution of approximately 1.5 mm. This design offers a compact, single-detector solution with high performance, which has great potential to simplify muon scattering tomography systems and further enhance image effect.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104080"},"PeriodicalIF":2.6,"publicationDate":"2025-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787534","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}
Pub Date : 2025-12-11DOI: 10.1016/j.net.2025.104076
John Wilkin F. Lim , Ray Matthew A. Bunquin , Angelo A. Panlaqui , Ronald E. Piquero
This study forecasts annual radioactive waste arisings for a Philippine baseline deployment of a ∼1200 MWe light-water reactor (LWR), with emphasis on high-level waste (HLW; spent fuel), intermediate-level waste (ILW), and low-level waste (LLW). The objective is to inform infrastructure planning, regulatory preparedness, and long-term waste management. A desk review synthesized unit-normalized data from reactors of comparable capacity in China, Sweden, Switzerland, the United Kingdom, and the United States of America, integrating internationally recognized benchmarks with country-specific operating information. Waste classes follow IAEA GSG-1. Indicative ranges are HLW: ∼18–33.6 tons/yr (dependent on fuel management, burnup, and capacity factor), ILW: ∼2–79 m3/yr (dominated by resins, filters, and selected activated components), and LLW: ∼30–250 m3/yr, with variance driven by burnup, capacity factor, coolant chemistry, purification practice, and outage schedule. These ranges provide defensible inputs for sizing storage, treatment/conditioning, transport, and disposal systems, and for aligning regulatory preparedness with IAEA safety requirements. Early adoption of HLW, ILW, and LLW management provisions based on these planning values will help safeguard public health and the environment while enabling a safe, economically credible introduction of nuclear power in the Philippines and supporting long-term policy and financing decisions.
{"title":"Anticipating radioactive waste: A forecast for the Philippines' upcoming nuclear energy","authors":"John Wilkin F. Lim , Ray Matthew A. Bunquin , Angelo A. Panlaqui , Ronald E. Piquero","doi":"10.1016/j.net.2025.104076","DOIUrl":"10.1016/j.net.2025.104076","url":null,"abstract":"<div><div>This study forecasts annual radioactive waste arisings for a Philippine baseline deployment of a ∼1200 MWe light-water reactor (LWR), with emphasis on high-level waste (HLW; spent fuel), intermediate-level waste (ILW), and low-level waste (LLW). The objective is to inform infrastructure planning, regulatory preparedness, and long-term waste management. A desk review synthesized unit-normalized data from reactors of comparable capacity in China, Sweden, Switzerland, the United Kingdom, and the United States of America, integrating internationally recognized benchmarks with country-specific operating information. Waste classes follow IAEA GSG-1. Indicative ranges are HLW: ∼18–33.6 tons/yr (dependent on fuel management, burnup, and capacity factor), ILW: ∼2–79 m<sup>3</sup>/yr (dominated by resins, filters, and selected activated components), and LLW: ∼30–250 m<sup>3</sup>/yr, with variance driven by burnup, capacity factor, coolant chemistry, purification practice, and outage schedule. These ranges provide defensible inputs for sizing storage, treatment/conditioning, transport, and disposal systems, and for aligning regulatory preparedness with IAEA safety requirements. Early adoption of HLW, ILW, and LLW management provisions based on these planning values will help safeguard public health and the environment while enabling a safe, economically credible introduction of nuclear power in the Philippines and supporting long-term policy and financing decisions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104076"},"PeriodicalIF":2.6,"publicationDate":"2025-12-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787532","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}
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