Pub Date : 2026-01-19DOI: 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.
{"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":"2026-01-19","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}
Pub Date : 2026-01-17DOI: 10.1016/j.net.2026.104136
Luis A. Montejo
While matching input motions to a design response spectrum (DRS) is standard practice, the US-NRC Standard Review Plan (SRP) 3.7.1 also mandates a minimum power spectral density (PSD) check to prevent power deficiencies that can lead to unconservative in-structure response spectra (ISRS). However, existing methodologies for constructing the required target PSD functions are designed for single-component analysis and do not accommodate the modern orientation-independent spectra (e.g., RotDnn) toward which bidirectional analysis is moving. This article addresses this gap by introducing an iterative algorithm to generate duration-dependent, orientation-independent PSD and Fourier Amplitude Spectra (FAS) functions compatible with any target RotDnn spectrum. The algorithm iteratively adjusts the target FAS of two orthogonal components until their combined RotDnn response spectrum provides a close match to the target DRS, from which a large set of synthetic motions is generated to define the final orientation-independent target spectra. The accuracy and robustness of the proposed methodology is demonstrated by successfully reproducing the FASRotD100 and PSDRotD100 from a benchmark dataset of 50 historical earthquake records, providing an essential tool for reliable seismic assessments consistent with modern hazard definitions.
{"title":"Generation of Fourier amplitude spectra and power spectral density functions compatible with orientation-independent design spectra for bidirectional seismic analyses of nuclear facilities","authors":"Luis A. Montejo","doi":"10.1016/j.net.2026.104136","DOIUrl":"10.1016/j.net.2026.104136","url":null,"abstract":"<div><div>While matching input motions to a design response spectrum (DRS) is standard practice, the US-NRC Standard Review Plan (SRP) 3.7.1 also mandates a minimum power spectral density (PSD) check to prevent power deficiencies that can lead to unconservative in-structure response spectra (ISRS). However, existing methodologies for constructing the required target PSD functions are designed for single-component analysis and do not accommodate the modern orientation-independent spectra (e.g., RotDnn) toward which bidirectional analysis is moving. This article addresses this gap by introducing an iterative algorithm to generate duration-dependent, orientation-independent PSD and Fourier Amplitude Spectra (FAS) functions compatible with any target RotDnn spectrum. The algorithm iteratively adjusts the target FAS of two orthogonal components until their combined RotDnn response spectrum provides a close match to the target DRS, from which a large set of synthetic motions is generated to define the final orientation-independent target spectra. The accuracy and robustness of the proposed methodology is demonstrated by successfully reproducing the FASRotD100 and PSDRotD100 from a benchmark dataset of 50 historical earthquake records, providing an essential tool for reliable seismic assessments consistent with modern hazard definitions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104136"},"PeriodicalIF":2.6,"publicationDate":"2026-01-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035815","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 : 2026-01-16DOI: 10.1016/j.net.2026.104144
Bub-Gyu Jeon , Sung-Wan Kim , Dong-Uk Park , Chae-Been Lee , DaeGi Hahm , Hong-Pyo Lee
Electrical cabinets are typically assembled in a multi-bay configuration, connecting two or more modules, and the structural implications of this setup must be carefully addressed. Concrete foundation cracks, often observed during field investigations at power plants, represent a common form of support deterioration. This study fabricated concrete foundations to simulate intact conditions and cracked conditions with 0.5 mm and 1.0 mm wide cracks at anchor locations. A simplified electrical cabinet model was constructed in single-bay, two-bay, and three-bay configurations and anchored to the concrete foundations using cast-in-place anchors to consider the effects of multi-bay configuration and support deterioration. Three-axis shaking table tests were conducted, including resonant frequency search and seismic fragility tests. The results indicated that cracks at the anchor locations can increase the uncertainty in the cabinet's resonant frequency. Specifically, when the concrete foundation was intact, seismic performance improved as the number of connected bays increased. However, cracks up to 1.0 mm in width degraded the seismic performance of multi-bay configurations but had a negligible impact on the single-bay cabinet. Moreover, distinct damage modes were observed between single-bay and multi-bay conditions.
{"title":"Seismic behavior of electrical cabinets with cast-in-place anchors: influence of concrete cracks and multi-bay installation","authors":"Bub-Gyu Jeon , Sung-Wan Kim , Dong-Uk Park , Chae-Been Lee , DaeGi Hahm , Hong-Pyo Lee","doi":"10.1016/j.net.2026.104144","DOIUrl":"10.1016/j.net.2026.104144","url":null,"abstract":"<div><div>Electrical cabinets are typically assembled in a multi-bay configuration, connecting two or more modules, and the structural implications of this setup must be carefully addressed. Concrete foundation cracks, often observed during field investigations at power plants, represent a common form of support deterioration. This study fabricated concrete foundations to simulate intact conditions and cracked conditions with 0.5 mm and 1.0 mm wide cracks at anchor locations. A simplified electrical cabinet model was constructed in single-bay, two-bay, and three-bay configurations and anchored to the concrete foundations using cast-in-place anchors to consider the effects of multi-bay configuration and support deterioration. Three-axis shaking table tests were conducted, including resonant frequency search and seismic fragility tests. The results indicated that cracks at the anchor locations can increase the uncertainty in the cabinet's resonant frequency. Specifically, when the concrete foundation was intact, seismic performance improved as the number of connected bays increased. However, cracks up to 1.0 mm in width degraded the seismic performance of multi-bay configurations but had a negligible impact on the single-bay cabinet. Moreover, distinct damage modes were observed between single-bay and multi-bay conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104144"},"PeriodicalIF":2.6,"publicationDate":"2026-01-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035814","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}
With the rapid development of high-repetition rate X-ray free electron laser (FEL), the issues of thermal deformation and stress in optical elements, such as mirrors, under high thermal loads have become increasingly prominent. Traditional design optimization relies on repeated Thermal-Structural coupling finite element simulations, which face bottlenecks, including low optimization efficiency and insufficient utilization of historical data. This paper proposes an optimization approach that combines PyAnsys parametric scanning with deep learning-based surface shape prediction, aiming to enhance the optimization efficiency of mirror cooling structures and support parameters. A parametric simulation platform is constructed using PyAnsys Geometry and PyMechanical, enabling the rapid generation of model variants within 30 s. Additionally, a historical database containing geometric features, physical parameters, and operating conditions is established. Furthermore, a deep neural network-based mirror height error prediction model is developed, and experiments show that the model can predict surface height errors with RMS <0.08 nm in water-cooled silicon mirror cases. This method has the potential to shorten the traditional design iteration cycle to a few hours, significantly enhancing data reuse. Future work should focus on incorporating incremental learning and physical constraints to improve the reliability of extrapolation for multi-condition scenarios and refine the optimization loop.
{"title":"The beamline optical component structural parameter optimization design based on PyAnsys and deep learning integration","authors":"Tong Li , Hao Zhou , Zhifeng Huang , Zhongmin Xu , Weiqing Zhang","doi":"10.1016/j.net.2026.104142","DOIUrl":"10.1016/j.net.2026.104142","url":null,"abstract":"<div><div>With the rapid development of high-repetition rate X-ray free electron laser (FEL), the issues of thermal deformation and stress in optical elements, such as mirrors, under high thermal loads have become increasingly prominent. Traditional design optimization relies on repeated Thermal-Structural coupling finite element simulations, which face bottlenecks, including low optimization efficiency and insufficient utilization of historical data. This paper proposes an optimization approach that combines PyAnsys parametric scanning with deep learning-based surface shape prediction, aiming to enhance the optimization efficiency of mirror cooling structures and support parameters. A parametric simulation platform is constructed using PyAnsys Geometry and PyMechanical, enabling the rapid generation of model variants within 30 s. Additionally, a historical database containing geometric features, physical parameters, and operating conditions is established. Furthermore, a deep neural network-based mirror height error prediction model is developed, and experiments show that the model can predict surface height errors with RMS <0.08 nm in water-cooled silicon mirror cases. This method has the potential to shorten the traditional design iteration cycle to a few hours, significantly enhancing data reuse. Future work should focus on incorporating incremental learning and physical constraints to improve the reliability of extrapolation for multi-condition scenarios and refine the optimization loop.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104142"},"PeriodicalIF":2.6,"publicationDate":"2026-01-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035720","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 : 2026-01-15DOI: 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.
{"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":"2026-01-15","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}
Pub Date : 2026-01-13DOI: 10.1016/j.net.2026.104133
Yupeng Li , Shengguo Wu , Xiaoke Wang , Jing Zheng , Yufei Wu , Xinnan Chen , Chunyu Gao , Chenyang Tang , Qiaoling Lu , Yang Liu , Xiuzhang Tang
This study presents cosmic-ray muon transmission imaging of a nuclear reactor. A high-spatial-resolution drift-tube muon tracker with an active area of 1.1 × 1.1 m2 was deployed at Unit 1 of a commercial nuclear power plant in China, which is a "Hualong One" pressurized water reactor, and operated for six months to record muon flux from various directions. Prior to fuel loading, a two-dimensional absorption map of the reactor was reconstructed from coincident muon events, which clearly resolved the reactor core and surrounding structures. After fuel loading, measurable changes in the absorption signal were observed in the fuel region. Monte Carlo simulations yielded reactor and core-specific imaging results that were in good agreement with the experimental measurements. In addition, the impact of tracker spatial resolution on image quality was analyzed. These findings indicate that muon transmission imaging is a promising method for reactor imaging.
{"title":"Experimental study on pressurized water reactor imaging using cosmic ray muons","authors":"Yupeng Li , Shengguo Wu , Xiaoke Wang , Jing Zheng , Yufei Wu , Xinnan Chen , Chunyu Gao , Chenyang Tang , Qiaoling Lu , Yang Liu , Xiuzhang Tang","doi":"10.1016/j.net.2026.104133","DOIUrl":"10.1016/j.net.2026.104133","url":null,"abstract":"<div><div>This study presents cosmic-ray muon transmission imaging of a nuclear reactor. A high-spatial-resolution drift-tube muon tracker with an active area of 1.1 × 1.1 m<sup>2</sup> was deployed at Unit 1 of a commercial nuclear power plant in China, which is a \"Hualong One\" pressurized water reactor, and operated for six months to record muon flux from various directions. Prior to fuel loading, a two-dimensional absorption map of the reactor was reconstructed from coincident muon events, which clearly resolved the reactor core and surrounding structures. After fuel loading, measurable changes in the absorption signal were observed in the fuel region. Monte Carlo simulations yielded reactor and core-specific imaging results that were in good agreement with the experimental measurements. In addition, the impact of tracker spatial resolution on image quality was analyzed. These findings indicate that muon transmission imaging is a promising method for reactor imaging.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104133"},"PeriodicalIF":2.6,"publicationDate":"2026-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035726","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 : 2026-01-13DOI: 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.
{"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":"2026-01-13","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}
Pub Date : 2026-01-13DOI: 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.
{"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":"2026-01-13","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}
Pub Date : 2026-01-13DOI: 10.1016/j.net.2026.104143
Thi Yen Hong Huynh , Huu Ngan Thy Truong , Ngoc Ba Vu
Accurate characterization of the HPGe detector dead layer is crucial for reliable Monte Carlo simulations in gamma-ray spectrometry. This study investigates the impact of source geometry on the determination of the effective dead layer thickness. Experimental measurements and MCNP6 simulations were conducted using a p-type coaxial HPGe detector with three geometries: a cylindrical source (S1), a 3π source (S2), and a Marinelli beaker (S3). Results show that while the physical dead layer distribution is intrinsic to the crystal, the determined effective dead layer parameter is strongly dependent on the irradiation geometry. The on-axis source (S1) indicated a stable frontal dead layer of approximately 0.60 mm. Conversely, volumetric sources (S2 and S3) revealed a thicker lateral dead layer (∼1.10–1.21 mm) with a significant transition zone at low energies due to the geometric weighting of photon interactions. Crucially, the study demonstrates that applying a uniform dead layer thickness derived from point-source calibration (S1) to volumetric geometries (S3) results in a systematic overestimation of efficiency across the energy range. These findings highlight the inadequacy of uniform dead layer models for complex geometries and the necessity of multi-region characterization for high-accuracy environmental monitoring.
{"title":"Impact of non-uniform dead layer distribution on efficiency calibration for volumetric sources in HPGe detectors","authors":"Thi Yen Hong Huynh , Huu Ngan Thy Truong , Ngoc Ba Vu","doi":"10.1016/j.net.2026.104143","DOIUrl":"10.1016/j.net.2026.104143","url":null,"abstract":"<div><div>Accurate characterization of the HPGe detector dead layer is crucial for reliable Monte Carlo simulations in gamma-ray spectrometry. This study investigates the impact of source geometry on the determination of the effective dead layer thickness. Experimental measurements and MCNP6 simulations were conducted using a p-type coaxial HPGe detector with three geometries: a cylindrical source (S1), a 3π source (S2), and a Marinelli beaker (S3). Results show that while the physical dead layer distribution is intrinsic to the crystal, the determined effective dead layer parameter is strongly dependent on the irradiation geometry. The on-axis source (S1) indicated a stable frontal dead layer of approximately 0.60 mm. Conversely, volumetric sources (S2 and S3) revealed a thicker lateral dead layer (∼1.10–1.21 mm) with a significant transition zone at low energies due to the geometric weighting of photon interactions. Crucially, the study demonstrates that applying a uniform dead layer thickness derived from point-source calibration (S1) to volumetric geometries (S3) results in a systematic overestimation of efficiency across the energy range. These findings highlight the inadequacy of uniform dead layer models for complex geometries and the necessity of multi-region characterization for high-accuracy environmental monitoring.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104143"},"PeriodicalIF":2.6,"publicationDate":"2026-01-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"146035811","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 : 2026-01-12DOI: 10.1016/j.net.2026.104127
Jun Liu , Hongfei Chen , Weizhuo Zhang , Renjie Niu , Ertao Li , Yuyang Chen
Serpentine concrete is an excellent neutron shielding material, and the addition of magnetite aggregate can enhance the γ-ray shielding performance of concrete. In this study, the Geant4 software was used to simulate and analyze five different concrete mix designs where magnetite aggregate replaced serpentine aggregate at varying concentrations. To ensure the reliability of the simulation results, the study compared them with the calculated data obtained from the Phy-X/PSD program. For both neutrons and γ-rays, several shielding parameters including linear attenuation coefficient (μ), half-value layer (HVL) and effective atomic number (Zeff) as well as effective electron density (Neff) were systematically calculated. Penetration rate and neutron energy spectrum analyses were also conducted. The results show that with the increase of magnetite doping, the γ-ray shielding performance of concrete is significantly enhanced, but the neutron shielding ability decreases. Based on a comprehensive evaluation of various performance indicators, the optimal proportion of magnetite aggregate was determined to be 25 %. The neutron shielding performance of this admixture is similar to that of pure serpentine concrete, while its γ-ray shielding performance is significantly improved.
{"title":"Neutron and γ-ray shielding properties of magnetite-serpentine concrete based on Geant4 simulation","authors":"Jun Liu , Hongfei Chen , Weizhuo Zhang , Renjie Niu , Ertao Li , Yuyang Chen","doi":"10.1016/j.net.2026.104127","DOIUrl":"10.1016/j.net.2026.104127","url":null,"abstract":"<div><div>Serpentine concrete is an excellent neutron shielding material, and the addition of magnetite aggregate can enhance the γ-ray shielding performance of concrete. In this study, the Geant4 software was used to simulate and analyze five different concrete mix designs where magnetite aggregate replaced serpentine aggregate at varying concentrations. To ensure the reliability of the simulation results, the study compared them with the calculated data obtained from the Phy-X/PSD program. For both neutrons and γ-rays, several shielding parameters including linear attenuation coefficient (<em>μ</em>), half-value layer (HVL) and effective atomic number (<em>Z</em><sub><em>eff</em></sub>) as well as effective electron density (<em>N</em><sub><em>eff</em></sub>) were systematically calculated. Penetration rate and neutron energy spectrum analyses were also conducted. The results show that with the increase of magnetite doping, the γ-ray shielding performance of concrete is significantly enhanced, but the neutron shielding ability decreases. Based on a comprehensive evaluation of various performance indicators, the optimal proportion of magnetite aggregate was determined to be 25 %. The neutron shielding performance of this admixture is similar to that of pure serpentine concrete, while its γ-ray shielding performance is significantly improved.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 5","pages":"Article 104127"},"PeriodicalIF":2.6,"publicationDate":"2026-01-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145980452","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}