Pub Date : 2025-12-31DOI: 10.1016/j.net.2025.104097
Chong Shik Park
The Mu2e experiment at Fermilab requires acceleration and transport of intense proton beams in order to deliver stable, uniform particle spills to the production target. To meet the experimental requirement, particles will be extracted slowly from the Delivery Ring to the external beamline. Using Synergia2, we have performed multi-particle tracking simulations of third-integer resonant extraction in the Delivery Ring, including space charge effects, physical beamline elements, and apertures. A piecewise linear ramp profile of tune quadrupoles was used to maintain a constant averaged spill rate throughout extraction. To study and minimize beam losses, we implemented and introduced a number of features, beamline element apertures, and septum plane alignments. Dynamic bumps are also implemented for local orbit corrections in which septum entrance angles are controlled to reduce angular spreads of extracted beams.
{"title":"Tracking simulation of third-integer resonant extraction for Fermilab’s Mu2e experiment","authors":"Chong Shik Park","doi":"10.1016/j.net.2025.104097","DOIUrl":"10.1016/j.net.2025.104097","url":null,"abstract":"<div><div>The Mu2e experiment at Fermilab requires acceleration and transport of intense proton beams in order to deliver stable, uniform particle spills to the production target. To meet the experimental requirement, particles will be extracted slowly from the Delivery Ring to the external beamline. Using <span>Synergia2</span>, we have performed multi-particle tracking simulations of third-integer resonant extraction in the Delivery Ring, including space charge effects, physical beamline elements, and apertures. A piecewise linear ramp profile of tune quadrupoles was used to maintain a constant averaged spill rate throughout extraction. To study and minimize beam losses, we implemented and introduced a number of features, beamline element apertures, and septum plane alignments. Dynamic bumps are also implemented for local orbit corrections in which septum entrance angles are controlled to reduce angular spreads of extracted beams.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104097"},"PeriodicalIF":2.6,"publicationDate":"2025-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145941452","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 : 2025-12-30DOI: 10.1016/j.net.2025.104111
Sung-Jun Lim , Sung-Hun Jo
This paper proposes a voltage-booster read-decoupled radiation-hardened 14T (BDRH14T) SRAM cell. In harsh environments such as space, radiation can flip the stored data in memory cells, resulting in soft errors, including single-event upset (SEU) and single-event multi-node upset (SEMNU). Moreover, with the continued scaling of CMOS technology, the reduced spacing between transistors lowers the critical charge, increasing the vulnerability of SRAM cells to radiation-induced faults. The proposed BDRH14T cell is designed to recover its original stored data at all sensitive nodes even under a high injected charge of 150 fC. Additionally, it is capable of self-recovery from SEMNU occurring at storage node pairs. In addition to its radiation hardness, the BDRH14T exhibits enhanced read stability and reduced power consumption, achieving high read static noise margin (RSNM) and hold static noise margin (HSNM), along with low hold power (HPWR). All simulations were conducted using a 90 nm CMOS technology, considering variations over a wide range of supply voltages (0.9–1.1 V) and temperatures (−30 °C–120 °C). The superior performance of BDRH14T is attributed to the adoption of a voltage booster, a read-decoupled architecture, and deliberate a trade-off in read and write access times (RAT and WAT).
{"title":"A multi-node-upset-resilient 14T SRAM with high read stability for space applications","authors":"Sung-Jun Lim , Sung-Hun Jo","doi":"10.1016/j.net.2025.104111","DOIUrl":"10.1016/j.net.2025.104111","url":null,"abstract":"<div><div>This paper proposes a voltage-booster read-decoupled radiation-hardened 14T (BDRH14T) SRAM cell. In harsh environments such as space, radiation can flip the stored data in memory cells, resulting in soft errors, including single-event upset (SEU) and single-event multi-node upset (SEMNU). Moreover, with the continued scaling of CMOS technology, the reduced spacing between transistors lowers the critical charge, increasing the vulnerability of SRAM cells to radiation-induced faults. The proposed BDRH14T cell is designed to recover its original stored data at all sensitive nodes even under a high injected charge of 150 fC. Additionally, it is capable of self-recovery from SEMNU occurring at storage node pairs. In addition to its radiation hardness, the BDRH14T exhibits enhanced read stability and reduced power consumption, achieving high read static noise margin (RSNM) and hold static noise margin (HSNM), along with low hold power (HPWR). All simulations were conducted using a 90 nm CMOS technology, considering variations over a wide range of supply voltages (0.9–1.1 V) and temperatures (−30 °C–120 °C). The superior performance of BDRH14T is attributed to the adoption of a voltage booster, a read-decoupled architecture, and deliberate a trade-off in read and write access times (RAT and WAT).</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104111"},"PeriodicalIF":2.6,"publicationDate":"2025-12-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980450","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 : 2025-12-30DOI: 10.1016/j.net.2025.104110
Sehwan Seol, Jae Chang Kim, Junehyung Lee Bernaski, Yong Kyun Kim, Ser Gi Hong
This study presents a novel method for estimating the masses of uranium-235 and total plutonium in spent nuclear fuel assemblies using only Differential Die-Away (DDA) analysis results and cooling time without relying on passive or delayed neutron measurements. A database of DDA signals was generated through MCNP6 simulations based on spent nuclear fuel compositions derived from ORIGAMI depletion calculations under a wide range of initial enrichments, burnups, and cooling times. The correlations were developed between DDA results (i.e., die-away time and total neutron counts) and the isotopic masses. For 235U, a linear function of the signal ratio was used with the coefficients depending on cooling time. For Pu, a separate correlation was introduced using the die-away time difference between spent and fresh fuels, which required an estimation of initial enrichment. A Gaussian Process Regression (GPR) model was trained for this purpose, achieving high accuracy. Validation with 50 independent SNFs showed high prediction performance with maximum relative errors of 7.52 % and 2.41 % for 235U and Pu, respectively. This method provides a non-destructive and efficient technique for characterizing spent nuclear fuel assemblies, offering potential applications in nuclear safeguards, spent fuel management, and nuclear material accountancy.
{"title":"New method for estimating uranium and plutonium masses using differential die-away signals","authors":"Sehwan Seol, Jae Chang Kim, Junehyung Lee Bernaski, Yong Kyun Kim, Ser Gi Hong","doi":"10.1016/j.net.2025.104110","DOIUrl":"10.1016/j.net.2025.104110","url":null,"abstract":"<div><div>This study presents a novel method for estimating the masses of uranium-235 and total plutonium in spent nuclear fuel assemblies using only Differential Die-Away (DDA) analysis results and cooling time without relying on passive or delayed neutron measurements. A database of DDA signals was generated through MCNP6 simulations based on spent nuclear fuel compositions derived from ORIGAMI depletion calculations under a wide range of initial enrichments, burnups, and cooling times. The correlations were developed between DDA results (i.e., die-away time and total neutron counts) and the isotopic masses. For <sup>235</sup>U, a linear function of the signal ratio was used with the coefficients depending on cooling time. For Pu, a separate correlation was introduced using the die-away time difference between spent and fresh fuels, which required an estimation of initial enrichment. A Gaussian Process Regression (GPR) model was trained for this purpose, achieving high accuracy. Validation with 50 independent SNFs showed high prediction performance with maximum relative errors of 7.52 % and 2.41 % for <sup>235</sup>U and Pu, respectively. This method provides a non-destructive and efficient technique for characterizing spent nuclear fuel assemblies, offering potential applications in nuclear safeguards, spent fuel management, and nuclear material accountancy.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104110"},"PeriodicalIF":2.6,"publicationDate":"2025-12-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145941449","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 : 2025-12-29DOI: 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.
{"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":"2025-12-29","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}
Pub Date : 2025-12-26DOI: 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.
{"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":"2025-12-26","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}
Pub Date : 2025-12-25DOI: 10.1016/j.net.2025.104102
Junhyuk Ha , Sang-Ho Lee , Jun-Yeop Lee
This study investigates the sorption behavior of Re(VII) onto bulk solid and colloidal phases of Bentonil-WRK bentonite under various reducing conditions. Reducing systems were established with Na2S2O4, disodium anthraquinone-2,6-disulfonate, and DB-3 groundwater from the KAERI Underground Research Tunnel (KURT). Batch sorption experiments were conducted for 2500 h with an initial Re(VII) concentration of 10−6.5 M and a solid-to-liquid ratio of 0.5 g/L. Measured pH and Eh values indicated the reduction of Re(VII) to Re(IV), consistent with thermodynamic predictions and confirmed by X-ray photoelectron spectroscopy. Sorption efficiency increased markedly after 500 h, highlighting the governing role of Re redox chemistry in such conditions. Faster sorption occurred in the DB-3 system, where Fe(II) ions and sulfur-bearing colloids enhanced Re retention. Sorption kinetic analysis indicated a redox-controlled sorption behavior of Re(VII) onto bulk solid and colloidal bentonite under the investigated reducing conditions. The results are expected to support more reliable predictions of the migration and retardation of redox-sensitive anionic radionuclides (e.g., Tc, for which Re serves as a chemical surrogate) in the reducing subsurface environment.
{"title":"Redox-controlled sorption behavior of Re(VII) on bulk solid and colloidal bentonite","authors":"Junhyuk Ha , Sang-Ho Lee , Jun-Yeop Lee","doi":"10.1016/j.net.2025.104102","DOIUrl":"10.1016/j.net.2025.104102","url":null,"abstract":"<div><div>This study investigates the sorption behavior of Re(VII) onto bulk solid and colloidal phases of Bentonil-WRK bentonite under various reducing conditions. Reducing systems were established with Na<sub>2</sub>S<sub>2</sub>O<sub>4</sub>, disodium anthraquinone-2,6-disulfonate, and DB-3 groundwater from the KAERI Underground Research Tunnel (KURT). Batch sorption experiments were conducted for 2500 h with an initial Re(VII) concentration of 10<sup>−6.5</sup> M and a solid-to-liquid ratio of 0.5 g/L. Measured pH and E<sub>h</sub> values indicated the reduction of Re(VII) to Re(IV), consistent with thermodynamic predictions and confirmed by X-ray photoelectron spectroscopy. Sorption efficiency increased markedly after 500 h, highlighting the governing role of Re redox chemistry in such conditions. Faster sorption occurred in the DB-3 system, where Fe(II) ions and sulfur-bearing colloids enhanced Re retention. Sorption kinetic analysis indicated a redox-controlled sorption behavior of Re(VII) onto bulk solid and colloidal bentonite under the investigated reducing conditions. The results are expected to support more reliable predictions of the migration and retardation of redox-sensitive anionic radionuclides (<em>e.g.</em>, Tc, for which Re serves as a chemical surrogate) in the reducing subsurface environment.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104102"},"PeriodicalIF":2.6,"publicationDate":"2025-12-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145925419","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 : 2025-12-25DOI: 10.1016/j.net.2025.104094
Faiza Sohail , Wahab Mubashir , Inamul Haq , Muhammad Zubair , Ali Mansoor , Haseeb ur Rehman
This paper provides detailed technical analysis of a hybrid energy system (HES) that integrates nuclear and solar energy sources, specifically focusing on optimizing electricity production and hydrogen generation. The study explores the potential of small modular reactors (SMRs), which are designed for flexibility of load following and frequency following modes. In this analysis, high temperature gas cooled SMR (design parameters are taken according to gas turbine high-temperature reactor (GT-HTR)), is thermodynamically coupled with a concentrated solar power (CSP) system, optimize in a way to enhance the performance and efficiency of the overall system. Solar thermal energy from CSP is used to reheat the gas in the second stage of a Brayton cycle, improving efficiency and regulating electricity output. During low-demand periods, surplus energy is diverted to hydrogen production using a solid oxide electrolysis cell (SOEC). In this study, the integration of CSP and hydrogen co-generation significantly improve the efficiency of the HTR with an electrical output of ranging from 225 to 450 MWe, and hydrogen production capacity of up to 130 tonnes/day.
{"title":"Technical analysis for optimum hydrogen production using nuclear–renewable hybrid energy system","authors":"Faiza Sohail , Wahab Mubashir , Inamul Haq , Muhammad Zubair , Ali Mansoor , Haseeb ur Rehman","doi":"10.1016/j.net.2025.104094","DOIUrl":"10.1016/j.net.2025.104094","url":null,"abstract":"<div><div>This paper provides detailed technical analysis of a hybrid energy system (HES) that integrates nuclear and solar energy sources, specifically focusing on optimizing electricity production and hydrogen generation. The study explores the potential of small modular reactors (SMRs), which are designed for flexibility of load following and frequency following modes. In this analysis, high temperature gas cooled SMR (design parameters are taken according to gas turbine high-temperature reactor (GT-HTR)), is thermodynamically coupled with a concentrated solar power (CSP) system, optimize in a way to enhance the performance and efficiency of the overall system. Solar thermal energy from CSP is used to reheat the gas in the second stage of a Brayton cycle, improving efficiency and regulating electricity output. During low-demand periods, surplus energy is diverted to hydrogen production using a solid oxide electrolysis cell (SOEC). In this study, the integration of CSP and hydrogen co-generation significantly improve the efficiency of the HTR with an electrical output of ranging from 225 to 450 MWe, and hydrogen production capacity of up to 130 tonnes/day.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104094"},"PeriodicalIF":2.6,"publicationDate":"2025-12-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145925333","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 : 2025-12-24DOI: 10.1016/j.net.2025.104101
Weikun Chen , Guoqiang Zhong , Bing Hong , Jian Liu
A miniaturized fast neutron imaging detector based on scintillating fiber (Sci-Fi) is designed to adopt a SiPM array as its photoelectric conversion component. The center of gravity (CoG) method, widely used for neutron event positioning, demonstrates limited effectiveness when applied to signals originating from the peripheral regions of the array. To address this issue, the present study conducted a simulation analysis of the light output distribution characteristics from both the Sci-Fi and the associated light guide using the Geant4 toolkit. The photon distribution functions fitted for various regions all exhibited correlation coefficients exceeding 0.99. Furthermore, this work categorized the deviations encountered during the operation of the imaging detector into three principal types: inherent deviations, hardware-induced deviations, and algorithmic deviations. Focusing on algorithmic deviations, scintillation photon events randomly distributed within the Sci-Fi array were simulated. An inversion method, developed based on the photon distribution function, employed an iterative computational approach to accurately determine event positions by optimizing the fit. Compared to the CoG method, the inversion technique achieves a reduction in average positional deviation by over 13 %, sustains robust positioning performance for events occurring near the array edges, enhances the effective utilization of the SiPM array, and is well-suited for applications demanding higher spatial resolution and an expanded field of view.
{"title":"Simulation study on event positioning algorithm of fast neutron imaging detector based on scintillating fiber and SiPM array","authors":"Weikun Chen , Guoqiang Zhong , Bing Hong , Jian Liu","doi":"10.1016/j.net.2025.104101","DOIUrl":"10.1016/j.net.2025.104101","url":null,"abstract":"<div><div>A miniaturized fast neutron imaging detector based on scintillating fiber (Sci-Fi) is designed to adopt a SiPM array as its photoelectric conversion component. The center of gravity (CoG) method, widely used for neutron event positioning, demonstrates limited effectiveness when applied to signals originating from the peripheral regions of the array. To address this issue, the present study conducted a simulation analysis of the light output distribution characteristics from both the Sci-Fi and the associated light guide using the Geant4 toolkit. The photon distribution functions fitted for various regions all exhibited correlation coefficients exceeding 0.99. Furthermore, this work categorized the deviations encountered during the operation of the imaging detector into three principal types: inherent deviations, hardware-induced deviations, and algorithmic deviations. Focusing on algorithmic deviations, scintillation photon events randomly distributed within the Sci-Fi array were simulated. An inversion method, developed based on the photon distribution function, employed an iterative computational approach to accurately determine event positions by optimizing the fit. Compared to the CoG method, the inversion technique achieves a reduction in average positional deviation by over 13 %, sustains robust positioning performance for events occurring near the array edges, enhances the effective utilization of the SiPM array, and is well-suited for applications demanding higher spatial resolution and an expanded field of view.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104101"},"PeriodicalIF":2.6,"publicationDate":"2025-12-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145925337","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}
In electromagnetic modeling of ion cyclotron range of frequencies (ICRF) antennas, curved coupling models provide a more realistic representation of the antenna and edge-plasma geometry, improving the accuracy of wave-coupling and loading predictions. However, limited radial space near the plasma boundary constrains the implementation of curved perfectly matched layers (PMLs), and field singularities may arise under such confined conditions. To investigate this issue, an idealized curved-domain model was formulated to analyze how curvature and the stretching function influence PML behavior. An analytical expression for the fast-wave reflection coefficient was derived and compared with finite-element simulations, which verified the analytical trends and revealed localized field enhancements associated with curvature and steep stretching. Building on these results, two-dimensional antenna–plasma coupling models incorporating J-TEXT–relevant parameters were used to evaluate PML performance under realistic spatial constraints. Planar models were also analyzed for reference. The 2D simulations show that stable absorption and smooth field distributions are maintained when the radial PML thickness lies within 0.12–0.13 m and the poloidal and toroidal PML spans satisfy θPMLp > 0.3 rad and θPMLt > 0.12 rad, with less than 2 % variation in coupled power. These results provide practical reference values for configuring curved PMLs in fusion-relevant electromagnetic simulations.
{"title":"Curvature-induced singularities and stability analysis of curved perfectly matched layers for ICRF antenna–plasma coupling","authors":"Wentao Geng, Donghui Xia, Xinyu Fang, Zhangsheng Huang, Yonghua Ding","doi":"10.1016/j.net.2025.104098","DOIUrl":"10.1016/j.net.2025.104098","url":null,"abstract":"<div><div>In electromagnetic modeling of ion cyclotron range of frequencies (ICRF) antennas, curved coupling models provide a more realistic representation of the antenna and edge-plasma geometry, improving the accuracy of wave-coupling and loading predictions. However, limited radial space near the plasma boundary constrains the implementation of curved perfectly matched layers (PMLs), and field singularities may arise under such confined conditions. To investigate this issue, an idealized curved-domain model was formulated to analyze how curvature and the stretching function influence PML behavior. An analytical expression for the fast-wave reflection coefficient was derived and compared with finite-element simulations, which verified the analytical trends and revealed localized field enhancements associated with curvature and steep stretching. Building on these results, two-dimensional antenna–plasma coupling models incorporating J-TEXT–relevant parameters were used to evaluate PML performance under realistic spatial constraints. Planar models were also analyzed for reference. The 2D simulations show that stable absorption and smooth field distributions are maintained when the radial PML thickness lies within 0.12–0.13 m and the poloidal and toroidal PML spans satisfy <em>θ</em><sub>PMLp</sub> > 0.3 rad and <em>θ</em><sub>PMLt</sub> > 0.12 rad, with less than 2 % variation in coupled power. These results provide practical reference values for configuring curved PMLs in fusion-relevant electromagnetic simulations.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104098"},"PeriodicalIF":2.6,"publicationDate":"2025-12-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145925334","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}
Nuclear power plant cogeneration with Multi-Effect Distillation (MED) offers a solution to provide both electricity and a freshwater supply in West Kalimantan. The influence of tropical seawater quality on the corrosion and scale formation potential and its implications for desalination performance were described. A physicochemical characterization of seawater quality for consistent feedwater is crucial to ensure desalination performance. Results indicated moderate corrosion rates (0.46–0.47 mm/year), driven largely by high chloride concentration, elevated TDS, and near-neutral pH. The content of Fe, Zn and Pb is potentially accelerating corrosion. In contrast, consistently negative LSI values (−1.83 to −2.44) confirmed negligible scaling potential but high corrosivity. Corrosion will accelerate material degradation, reduce thermal efficiency, and decrease the ratio between the amount of distillate produced and steam used. This also impacts the reliability and safety of nuclear installations, which require a freshwater supply for cooling systems. These findings emphasize corrosion as the critical operational challenge and highlight the need for corrosion-resistant materials, protective coatings, cathodic protection, and advanced pretreatment to ensure safe and sustainable MED–nuclear cogeneration systems in coastal environments.
{"title":"Challenges and mitigations of corrosion and scale in nuclear cogeneration desalination systems: A case study from West Kalimantan","authors":"Siti Alimah , Sriyono , June Mellawati , Sudi Ariyanto , Sunarko , Akhmad Muktaf Haifani , Djati Hoesen Salimy , Yuni Indrawati , Khusnul Khotimah","doi":"10.1016/j.net.2025.104100","DOIUrl":"10.1016/j.net.2025.104100","url":null,"abstract":"<div><div>Nuclear power plant cogeneration with Multi-Effect Distillation (MED) offers a solution to provide both electricity and a freshwater supply in West Kalimantan. The influence of tropical seawater quality on the corrosion and scale formation potential and its implications for desalination performance were described. A physicochemical characterization of seawater quality for consistent feedwater is crucial to ensure desalination performance. Results indicated moderate corrosion rates (0.46–0.47 mm/year), driven largely by high chloride concentration, elevated TDS, and near-neutral pH. The content of Fe, Zn and Pb is potentially accelerating corrosion. In contrast, consistently negative LSI values (−1.83 to −2.44) confirmed negligible scaling potential but high corrosivity. Corrosion will accelerate material degradation, reduce thermal efficiency, and decrease the ratio between the amount of distillate produced and steam used. This also impacts the reliability and safety of nuclear installations, which require a freshwater supply for cooling systems. These findings emphasize corrosion as the critical operational challenge and highlight the need for corrosion-resistant materials, protective coatings, cathodic protection, and advanced pretreatment to ensure safe and sustainable MED–nuclear cogeneration systems in coastal environments.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104100"},"PeriodicalIF":2.6,"publicationDate":"2025-12-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145925418","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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