Pub Date : 2026-04-01Epub 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":"2026-04-01","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 : 2026-04-01Epub Date: 2025-12-02DOI: 10.1016/j.net.2025.104062
Jin-Wei Wang , Jiaojiao Li
Tiny nuclear batteries (TNBs) are one of the cutting-edge technologies to meet the future sustainable energy needs of residents, and will play an important role in the future modern low-carbon energy system. However, the public's adoption intention of this new technology and its influencing mechanism are still unclear. This study expanded the technology acceptance model of TNBs from the perspective of risk and sustainable development, analyzed 387 questionnaires collected in Beijing in depth, and revealed the key transmission path affecting TNBs' adoption intention using structural equation modeling and the bootstrap technique. In the context of Beijing, the results indicate that Hazardous Materials Risk (HMR), Performance Risk (PR), and Sustainable Development Goals (SDGs) have only indirect effects on the Behavioral Intention (BI) of TNBs, and Green Perceived Usefulness (GPU) is an important mediating variable. In addition, this study found that "ever heard of TNBs" (EH) is an important moderating variable. If one had been aware of TNBs in advance, the total indirect effect of PR would have been significantly increased by 0.212.
{"title":"Risk concerns and sustainable development goals influencing the adoption of tiny nuclear batteries: Findings from public perceptions","authors":"Jin-Wei Wang , Jiaojiao Li","doi":"10.1016/j.net.2025.104062","DOIUrl":"10.1016/j.net.2025.104062","url":null,"abstract":"<div><div>Tiny nuclear batteries (TNBs) are one of the cutting-edge technologies to meet the future sustainable energy needs of residents, and will play an important role in the future modern low-carbon energy system. However, the public's adoption intention of this new technology and its influencing mechanism are still unclear. This study expanded the technology acceptance model of TNBs from the perspective of risk and sustainable development, analyzed 387 questionnaires collected in Beijing in depth, and revealed the key transmission path affecting TNBs' adoption intention using structural equation modeling and the bootstrap technique. In the context of Beijing, the results indicate that Hazardous Materials Risk (HMR), Performance Risk (PR), and Sustainable Development Goals (SDGs) have only indirect effects on the Behavioral Intention (BI) of TNBs, and Green Perceived Usefulness (GPU) is an important mediating variable. In addition, this study found that \"ever heard of TNBs\" (EH) is an important moderating variable. If one had been aware of TNBs in advance, the total indirect effect of PR would have been significantly increased by 0.212.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104062"},"PeriodicalIF":2.6,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145734736","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 : 2026-04-01Epub 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":"2026-04-01","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 : 2026-04-01Epub Date: 2025-12-08DOI: 10.1016/j.net.2025.104070
Bong Young Kim , Seong-Kyu Ahn
A safeguardability evaluation methodology was developed to support the implementation of safeguards by design (SBD) approach. Evaluation factors were derived and classified into quantitative and qualitative factors. The evaluation methodology comprises five steps. Step 1 involves defining a set of design information for the facility. Step 2 involves defining a set of safeguards measures for the facility. Step 3 involves setting the diversion time for each diversion pathway. Step 4 involves producing a fault tree and examining the diversion detection probability. Step 5 involves quantitative analysis of various diversion pathways and qualitative analysis. Moreover, a safeguardability evaluation tool (SET) capable of implementing these steps was developed. Whereas previous studies on proliferation resistance or safeguardability have mainly relied on qualitative or comparative analyses, this study introduced a structured and executable methodology that enables quantitative, scenario-based, and regulation-aligned evaluation of safeguardability. The implementation of this method in the SET provides a practical foundation for operationalizing the IAEA's SBD principle in both the design and regulatory review stages of new nuclear facilities, including advanced and non-traditional types.
{"title":"A practical safeguardability evaluation framework and tool supporting SBD implementation for new nuclear facilities","authors":"Bong Young Kim , Seong-Kyu Ahn","doi":"10.1016/j.net.2025.104070","DOIUrl":"10.1016/j.net.2025.104070","url":null,"abstract":"<div><div>A safeguardability evaluation methodology was developed to support the implementation of safeguards by design (SBD) approach. Evaluation factors were derived and classified into quantitative and qualitative factors. The evaluation methodology comprises five steps. Step 1 involves defining a set of design information for the facility. Step 2 involves defining a set of safeguards measures for the facility. Step 3 involves setting the diversion time for each diversion pathway. Step 4 involves producing a fault tree and examining the diversion detection probability. Step 5 involves quantitative analysis of various diversion pathways and qualitative analysis. Moreover, a safeguardability evaluation tool (SET) capable of implementing these steps was developed. Whereas previous studies on proliferation resistance or safeguardability have mainly relied on qualitative or comparative analyses, this study introduced a structured and executable methodology that enables quantitative, scenario-based, and regulation-aligned evaluation of safeguardability. The implementation of this method in the SET provides a practical foundation for operationalizing the IAEA's SBD principle in both the design and regulatory review stages of new nuclear facilities, including advanced and non-traditional types.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104070"},"PeriodicalIF":2.6,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787948","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 : 2026-04-01Epub Date: 2025-12-23DOI: 10.1016/j.net.2025.104093
Dakyoung Lee , Sung-yeop Kim , Gibeom Kim , Eung Soo Kim
In Level 3 probabilistic safety assessment (PSA), accurate modeling of atmospheric dispersion is essential for predicting radionuclide concentrations and radiation doses. As a key input to the commonly used Gaussian plume model, the dispersion coefficient directly affects the reliability of offsite consequence assessments. This study compares six representative dispersion coefficient models and quantitatively evaluates how differences among them influence ground-level dilution and mean peak dose estimates. Simulations were conducted using RCAP and MACCS, two consequence assessment codes. Despite some numerical differences, both tools showed consistent trends, with the results demonstrating that the choice of dispersion model can lead to variations of up to 2.65 times in dilution and 1.77 times in dose. Sensitivity analyses revealed that wind speed has a significant impact on model variability and uncertainty, while plume release height has a negligible effect. Overall, the Briggs model produced the most conservative estimates, whereas the Modified Tadmor–Gur model showed the least conservative tendencies. These findings underscore the importance of selecting appropriate dispersion models in Level 3 PSA, as the choice may significantly influence key decisions such as the emergency planning zone boundaries. The results also help to support the credibility and precision of future consequence assessments.
{"title":"Impact of dispersion coefficient models on offsite consequence analyses","authors":"Dakyoung Lee , Sung-yeop Kim , Gibeom Kim , Eung Soo Kim","doi":"10.1016/j.net.2025.104093","DOIUrl":"10.1016/j.net.2025.104093","url":null,"abstract":"<div><div>In Level 3 probabilistic safety assessment (PSA), accurate modeling of atmospheric dispersion is essential for predicting radionuclide concentrations and radiation doses. As a key input to the commonly used Gaussian plume model, the dispersion coefficient directly affects the reliability of offsite consequence assessments. This study compares six representative dispersion coefficient models and quantitatively evaluates how differences among them influence ground-level dilution and mean peak dose estimates. Simulations were conducted using RCAP and MACCS, two consequence assessment codes. Despite some numerical differences, both tools showed consistent trends, with the results demonstrating that the choice of dispersion model can lead to variations of up to 2.65 times in dilution and 1.77 times in dose. Sensitivity analyses revealed that wind speed has a significant impact on model variability and uncertainty, while plume release height has a negligible effect. Overall, the Briggs model produced the most conservative estimates, whereas the Modified Tadmor–Gur model showed the least conservative tendencies. These findings underscore the importance of selecting appropriate dispersion models in Level 3 PSA, as the choice may significantly influence key decisions such as the emergency planning zone boundaries. The results also help to support the credibility and precision of future consequence assessments.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104093"},"PeriodicalIF":2.6,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145977207","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 : 2026-04-01Epub Date: 2025-12-02DOI: 10.1016/j.net.2025.104063
Ya-Qi Zhong , Zhi-Hong Liu , Hai-Biao Ji , Rui Wang , Jian-Guo Ma , Yu-Dong Su , Hua Zhai
In nuclear fusion engineering, high residual tensile stresses post-weld critically undermine structural integrity by reducing fatigue strength, accelerating crack propagation, and increasing the risk of failure. Alleviating residual tensile stresses in thick-section 316L austenitic stainless steel continues to be a significant scientific and engineering issue. This study investigated the effects of ultrasonic vibratory stress relief (UVSR) and ultrasonic impact treatment (UIT) through 4 customized process schemes: layer-by-layer UVSR, post-weld UVSR, and the UIT-UVSR composite process. The distribution of residual stress, microstructure, and mechanical properties of welded joints in fusion reactor vacuum vessel components were thoroughly assessed. All four schemes diminished welding residual stresses, enhanced the microstructure, and elevated local mechanical characteristics. Significantly, post-weld UVSR attained optimal stress relief, diminishing longitudinal and transverse residual stresses by 51.2 % and 25 %, respectively, while facilitating a more uniform stress distribution. The UIT-UVSR composite processes could not demonstrate synergy beyond individual UVSR, and layer-by-layer UVSR proved less effective than post-weld UVSR. In summary, post-weld UVSR is an efficient technique for regulating residual stresses in thick-section 316L welds, offering practical insights for components of fusion-reactor vacuum vessels.
{"title":"Research on the regulation of welding residual stress in 316L austenitic stainless steel thick-section based on ultrasonic impact and vibration","authors":"Ya-Qi Zhong , Zhi-Hong Liu , Hai-Biao Ji , Rui Wang , Jian-Guo Ma , Yu-Dong Su , Hua Zhai","doi":"10.1016/j.net.2025.104063","DOIUrl":"10.1016/j.net.2025.104063","url":null,"abstract":"<div><div>In nuclear fusion engineering, high residual tensile stresses post-weld critically undermine structural integrity by reducing fatigue strength, accelerating crack propagation, and increasing the risk of failure. Alleviating residual tensile stresses in thick-section 316L austenitic stainless steel continues to be a significant scientific and engineering issue. This study investigated the effects of ultrasonic vibratory stress relief (UVSR) and ultrasonic impact treatment (UIT) through 4 customized process schemes: layer-by-layer UVSR, post-weld UVSR, and the UIT-UVSR composite process. The distribution of residual stress, microstructure, and mechanical properties of welded joints in fusion reactor vacuum vessel components were thoroughly assessed. All four schemes diminished welding residual stresses, enhanced the microstructure, and elevated local mechanical characteristics. Significantly, post-weld UVSR attained optimal stress relief, diminishing longitudinal and transverse residual stresses by 51.2 % and 25 %, respectively, while facilitating a more uniform stress distribution. The UIT-UVSR composite processes could not demonstrate synergy beyond individual UVSR, and layer-by-layer UVSR proved less effective than post-weld UVSR. In summary, post-weld UVSR is an efficient technique for regulating residual stresses in thick-section 316L welds, offering practical insights for components of fusion-reactor vacuum vessels.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104063"},"PeriodicalIF":2.6,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145734737","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":"2026-04-01","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 : 2026-04-01Epub Date: 2025-10-15DOI: 10.1016/j.net.2025.103978
Jiung Kim, Tae Young Kong
In Korean pressurized heavy water reactors (PHWRs), the tritium removal facility (TRF) has been operational since 2007 to minimize tritium discharges into the environment. This study examined the impact of the TRF on tritium discharges from Korean PHWRs. Before the TRF was implemented, the average annual tritium discharge over a 10-year period was 4.44 × 1014 Bq y−1. However, after the TRF commenced operation, this average annual discharge was reduced to 2.89 × 1014 Bq y−1 over the following 10 years, representing a decrease of approximately 35 %. The introduction of the TRF has played a significant role in lowering the amount of tritium released from Korean PHWRs, thereby minimizing its impact on the surrounding environment and the health of local residents. Therefore, it is essential to continue the operation of the TRF and monitor tritium discharges to effectively manage the radiological risks associated with tritium discharges from Korean PHWRs, while protecting the surrounding environment and public health.
{"title":"Analysis of the changes in tritium discharges from Korean pressurized heavy water reactors due to the operation of tritium removal facilities","authors":"Jiung Kim, Tae Young Kong","doi":"10.1016/j.net.2025.103978","DOIUrl":"10.1016/j.net.2025.103978","url":null,"abstract":"<div><div>In Korean pressurized heavy water reactors (PHWRs), the tritium removal facility (TRF) has been operational since 2007 to minimize tritium discharges into the environment. This study examined the impact of the TRF on tritium discharges from Korean PHWRs. Before the TRF was implemented, the average annual tritium discharge over a 10-year period was 4.44 × 10<sup>14</sup> Bq y<sup>−1</sup>. However, after the TRF commenced operation, this average annual discharge was reduced to 2.89 × 10<sup>14</sup> Bq y<sup>−1</sup> over the following 10 years, representing a decrease of approximately 35 %. The introduction of the TRF has played a significant role in lowering the amount of tritium released from Korean PHWRs, thereby minimizing its impact on the surrounding environment and the health of local residents. Therefore, it is essential to continue the operation of the TRF and monitor tritium discharges to effectively manage the radiological risks associated with tritium discharges from Korean PHWRs, while protecting the surrounding environment and public health.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 103978"},"PeriodicalIF":2.6,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145692862","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 : 2026-04-01Epub 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":"2026-04-01","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 : 2026-04-01Epub Date: 2025-12-04DOI: 10.1016/j.net.2025.104067
Hyeong Jin Kim, Hyeongju Bae, Ho Jin Ryu
The hydration behavior of gadolinium oxide (Gd2O3) under high-temperature water conditions presents a significant challenge for the development of soluble-boron-free small modular reactor (SMR) fuels. To overcome this issue, we investigated cerium oxide (CeO2) additions to improve the hydration resistance of Gd2O3. Pellets containing 0–25 at.% Ce were exposed to pressurized water at 200 °C, 1.5 MPa, for 48 h. Gd2O3 pellets are originally monoclinic under 1600 °C sintering temperature, whereas CeO2 additions progressively suppress the phase transformation; at 15 at.% or higher Ce doping, a single cubic phase forms. XRD showed that undoped Gd2O3 fully hydrates, whereas specimens with 15 at.% or higher Ce doping retain the cubic structure with no detectable hydroxides. FT-IR results also provide evidence of hydration resistance of Ce-doped Gd2O3, by vanishing Gd-O-H bands with the Ce addition. XPS indicated that Ce ions are predominantly Ce4+ in 15 at.% or higher Ce-doped Gd2O3, suggesting that Ce4+ substitution on Gd3+ sites prevents oxygen-vacancy-assisted hydroxylation. Conversely, a lower Ce4+ fraction in pellets sintered in an Ar atmosphere correlated with an increased hydration tendency. These results indicate that 15 at.% or higher Ce doping stabilizes the cubic phase of Gd2O3 and completely suppresses hydration under the tested conditions, as a result of a reduced oxygen vacancy concentration.
{"title":"Improving hydration resistance of gadolinium-based burnable absorbers via cerium oxide additions","authors":"Hyeong Jin Kim, Hyeongju Bae, Ho Jin Ryu","doi":"10.1016/j.net.2025.104067","DOIUrl":"10.1016/j.net.2025.104067","url":null,"abstract":"<div><div>The hydration behavior of gadolinium oxide (Gd<sub>2</sub>O<sub>3</sub>) under high-temperature water conditions presents a significant challenge for the development of soluble-boron-free small modular reactor (SMR) fuels. To overcome this issue, we investigated cerium oxide (CeO<sub>2</sub>) additions to improve the hydration resistance of Gd<sub>2</sub>O<sub>3</sub>. Pellets containing 0–25 at.% Ce were exposed to pressurized water at 200 °C, 1.5 MPa, for 48 h. Gd<sub>2</sub>O<sub>3</sub> pellets are originally monoclinic under 1600 °C sintering temperature, whereas CeO<sub>2</sub> additions progressively suppress the phase transformation; at 15 at.% or higher Ce doping, a single cubic phase forms. XRD showed that undoped Gd<sub>2</sub>O<sub>3</sub> fully hydrates, whereas specimens with 15 at.% or higher Ce doping retain the cubic structure with no detectable hydroxides. FT-IR results also provide evidence of hydration resistance of Ce-doped Gd<sub>2</sub>O<sub>3</sub>, by vanishing Gd-O-H bands with the Ce addition. XPS indicated that Ce ions are predominantly Ce<sup>4+</sup> in 15 at.% or higher Ce-doped Gd<sub>2</sub>O<sub>3</sub>, suggesting that Ce<sup>4+</sup> substitution on Gd<sup>3+</sup> sites prevents oxygen-vacancy-assisted hydroxylation. Conversely, a lower Ce<sup>4+</sup> fraction in pellets sintered in an Ar atmosphere correlated with an increased hydration tendency. These results indicate that 15 at.% or higher Ce doping stabilizes the cubic phase of Gd<sub>2</sub>O<sub>3</sub> and completely suppresses hydration under the tested conditions, as a result of a reduced oxygen vacancy concentration.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104067"},"PeriodicalIF":2.6,"publicationDate":"2026-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145734677","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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