Nuclear Engineering and Design最新文献

{"title":"Characteristics of oxygen mass transfer in a pneumatic mass exchanger for solid-phase oxygen control in the lead bismuth","authors":"Zhen Yang,&nbsp;Haicai Lyu,&nbsp;Honglin Zhou,&nbsp;Fang Liu,&nbsp;Weihao Xing,&nbsp;Shengfei Wang,&nbsp;Wentao Guo,&nbsp;Zhangpeng Guo,&nbsp;Ruixian Liang,&nbsp;Fenglei Niu","doi":"10.1016/j.nucengdes.2025.114022","DOIUrl":"10.1016/j.nucengdes.2025.114022","url":null,"abstract":"<div><div>Oxygen concentration in lead–bismuth alloy (LBE) systems has a significant effect on the corrosion rate of structural materials. The corrosion of structural materials by LBE can be effectively mitigated by dynamically adjusting the dissolved oxygen concentration in liquid lead–bismuth. Solid-phase oxygen control technology comprised of a packed bed of lead oxide spheres is widely recognized as an effect and promising solution to regulate the dissolved oxygen concentration, in which how to quantitatively regulate the supplemental solid-phase PbO oxygen source is the key to solid-phase oxygen control technology. This paper innovatively designs a pneumatic mass exchanger for controllable oxygenation without moving parts, and experimentally investigates the oxygen mass transfer characteristics under different temperatures, relative flow velocities, and surface areas of oxygen source areas. By combining an empirical oxygen mass transfer model and the oxygen mass conservation equation, a theoretical prediction model for the reciprocating pneumatic mass exchanger is developed. The results indicate that temperature can rapidly adjust the oxygen dissolution rate, while the relative flow velocity can be used as an effective measure to precisely control the oxygen concentration. The oxygen dissolution rate is directly proportional to the oxygen source surface area. The average relative error of the oxygen concentration between the theoretical prediction model and experimental results is 1.65, with the deviation primarily attributed to discrepancies in oxygen diffusion and the fitting of the mass transfer empirical model. The oxygen concentration in lead–bismuth can be controlled within a reasonable range, thereby validating the oxygenation performance of the novel solid-state oxygen control device—the pneumatic mass exchanger.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114022"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759373","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}

{"title":"Simplified models for high burnup spent nuclear fuel rods and their comparison","authors":"Seyeon Kim,&nbsp;Sanghoon Lee","doi":"10.1016/j.nucengdes.2025.114032","DOIUrl":"10.1016/j.nucengdes.2025.114032","url":null,"abstract":"<div><div>Effective management of spent nuclear fuel requires maintaining its structural integrity with safety guidelines emphasizing protection of the cladding from mechanical and physical damage that could lead to significant fuel rod failure. According to NUREG-1864, the plastic strain that can cause cladding failure was observed to be in the range of 1.0 ∼ 4.0 %. The experimental data was obtained by pressurized tube tests with defueled cladding specimens and could not reflect the complicated stress states due to the pellet-clad interaction that occurs in real drop impacts. However, the failure criterion of irradiated cladding under more complicated stress states is not easily available. In this study, we perform a comparative analysis of the applicability of simplified models for an SNF rod based on two new fracture criteria and flexural rigidity modification proposed in NUREG-2224. The two new failure criteria utilize curvature based plastic bending strain and membrane plus bending stress through the thickness of the cladding, respectively. Of the three models, the simplified model based on membrane plus bending stress failure criterion was found to be the most conservative in dynamic impact applications.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114032"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759446","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Investigation of stress corrosion crack propagation characteristics and life prediction for thick-walled double U-groove pipe welds in PWR steam generator","authors":"Baoyin Zhu ,&nbsp;Zheng He ,&nbsp;Lu Zhang ,&nbsp;Shuitao Gu ,&nbsp;Xiao Jin ,&nbsp;Dungui Zuo ,&nbsp;Gongye Zhang","doi":"10.1016/j.nucengdes.2025.114019","DOIUrl":"10.1016/j.nucengdes.2025.114019","url":null,"abstract":"<div><div>Stress corrosion cracking (SCC) is a critical concern in evaluating the structural integrity of pressurized water reactor (PWR) primary pressure boundaries. Material mismatch and welding-induced residual stresses introduce significant challenges in predicting crack propagation paths and service-induced defect lifetimes. This study examines the influence of welding residual stress on SCC in a thick-walled double U-groove pipe dissimilar steel welded joint of a PWR steam generator (SG), and assesses the propagation life of SCC from an engineering standpoint. First, the distribution and stress state of residual stresses in complex SG dissimilar steel joints were analyzed using the two-way thermal coupling finite element method to establish initial stress boundary conditions for simulating SCC propagation influenced by residual stresses. Next, the extended finite element method combined with the maximum principal stress criterion was employed to investigate the propagation direction and path of cracks originating from various initial positions due to welding residual stresses. Concurrently, the J-integral method was used to calculate the stress intensity factors of cracks at different depths along the propagation path. Finally, based on the modified Shoji model, the relationship between the stress intensity factor and SCC propagation rate was examined, allowing for predictions of crack propagation rates and service life for SCC with varying initial defects.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114019"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759445","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}

{"title":"Functionally adaptable isolated structures for small modular reactors based on design demands","authors":"Kui Yang ,&nbsp;Ping Tan ,&nbsp;Jiying Shang ,&nbsp;Yafei Zhang ,&nbsp;Jiaxi Li","doi":"10.1016/j.nucengdes.2025.114037","DOIUrl":"10.1016/j.nucengdes.2025.114037","url":null,"abstract":"<div><div>Nuclear power plants are gradually trending toward miniaturization and standardization owing to their expensive costs, lengthy design cycles, challenging siting, and hazardous issues. However, this development presents challenges such as reduced site adaptability and weakened seismic capacity. In response to the above challenges, this paper proposes a multifunctional combination-rail tension friction slip isolator (MC-RTFSI). Its application enables small modular reactors (SMRs) to satisfy the requirements of different sites and seismic intensities without the necessity of modifying the design. MC-RTFSI is a composite system comprising different types of sliding rails that exhibit distinct mechanical properties. The selection of suitable rails is based on the specific characteristics of different sites. Furthermore, it exhibits performance decoupling in both orthogonal directions and uplift-restraining properties. Various combinations of MC-RTFSI were mechanically investigated, leading to the construction of a mechanical hysteresis model. This model was subsequently simulated by employing series–parallel combinations of nonlinear units in current finite element analysis software (ETABS, SAP 2000). Based on the result of the refined finite element simulation, the effectiveness of the simulated units is confirmed. A number of nonlinear response history analyses were conducted. The results indicate that novel isolated structures for small-scale nuclear power plants possess the capacity to perform various activities and may be adapted to accommodate different sites and ground motion characteristics.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114037"},"PeriodicalIF":1.9,"publicationDate":"2025-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143748236","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}

{"title":"Efficient adsorption of Cs(I) and Sr(II) ions from solution by xanthate modified sponge-like chitosan","authors":"Bowen Xu ,&nbsp;Tian Huiyu ,&nbsp;Chen Jianbo ,&nbsp;Wei Lifeng ,&nbsp;Wang Kai ,&nbsp;Jianlong Wang","doi":"10.1016/j.nucengdes.2025.114031","DOIUrl":"10.1016/j.nucengdes.2025.114031","url":null,"abstract":"<div><div>Efficient removal of radionuclides from radioactive wastewater is vital for ensuring the sustainable development of nuclear energy. Herein, xanthate-modified sponge-like chitosan-based adsorbent (CTS-SX) was synthesized through a facile method, which exhibited excellent adsorption performance for Sr(II) and Cs(I). The maximum adsorption capacity of Sr(II) and Cs(I) reached 76.21 and 133.15 mg·g⁻¹ respectively. Various models were used to fit the adsorption process, and the results indicated that the adsorption process of Sr(II) was best fitted by Freundlich isotherm model and phenomenological internal mass transfer kinetic model, while the adsorption of Cs(I) was best fitted by Langmuir isotherm model and Langmuir kinetics model. In addition, the adsorption performance in binary-component system, influence of pH and competing ions were also explored. In summary, the modification could improve the amount of active sites and hydrophobility of CTS-SX. With excellent adsorption performance and simplicity of separation, CTS-SX has potential in application for radioactive wastewater treatment.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114031"},"PeriodicalIF":1.9,"publicationDate":"2025-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143748235","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}

{"title":"Neutronic design space exploration for salt-cooled reactor system based on advanced gas-cooled reactor technology","authors":"Zhiyao Xing ,&nbsp;Paul Cosgrove ,&nbsp;Marat Margulis ,&nbsp;Eugene Shwageraus","doi":"10.1016/j.nucengdes.2025.114000","DOIUrl":"10.1016/j.nucengdes.2025.114000","url":null,"abstract":"<div><div>Fluoride-salt-cooled High-temperature Reactors (FHRs) offer high power densities and operating temperatures. The current paper continues to explore the possibility to leverage the knowledge gathered in the operation of British Advanced Gas-cooled Reactor (AGR) fleet to expedite the FHR deployment. The paper looks into the neutronic performance of the potential fuel assembly inside the thermal-hydraulics optimised space. Neutronic simulations were performed at Beginning of Life conditions to identify design streams that demonstrated potential for the most favourable fuel cycle economic performance and other strategic advantages such as tritium-free NaF-ZrF₄ coolant. The study identified several possible assembly configurations with favourable neutronic performance (i.e., negative coolant temperature coefficient). The designs were considered best performing where no further modification of the design parameters led to simultaneous improvement in both k_∞ and CTC. The best performing configuration contained FLiBe, uranium-carbide fuel and a small volume fraction of graphite.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114000"},"PeriodicalIF":1.9,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143748233","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design and integrated performance estimate of a solar-nuclear hybrid energy power generation system","authors":"Yifan Wang ,&nbsp;Ran Zhang ,&nbsp;Yu Liang ,&nbsp;Xiao Liu ,&nbsp;Meiyue Yan ,&nbsp;Simiao Tang ,&nbsp;Luteng Zhang ,&nbsp;Liangming Pan","doi":"10.1016/j.nucengdes.2025.114018","DOIUrl":"10.1016/j.nucengdes.2025.114018","url":null,"abstract":"<div><div>In order to promote the global green energy transition and improve the availability of intermittent renewable energy, a thermodynamic power generation system with hybrid solar and nuclear energy is designed in this paper. The hybrid energy system includes a tower solar concentrating thermal module, a High Temperature Gas-cooled Reactor module and a recompression Brayton cycle power generation module. The sodium nitrate-potassium nitrate molten salt is utilized for heat transfer and storage. The EBSILON simulation software is used for model simulation and operational analysis of the system. The effects of different working fluids (S-CO₂, He, He-Xe, N₂, Air) and solar radiation parameters on the power generation performance of the system are investigated. The results show that the power generation efficiency increases with the elevation of turbine inlet pressure, but the efficiency gain is lower with the increase of pressure due to amplified exergy loss. The power generation efficiency of the system increases proportionally to the increase of turbine inlet temperature. Comparative analysis confirms the utilization of S-CO₂ can achieve higher efficiency than the other four fluids and its optimal split ratio is 0.279. As the maximum pressure of the cycle increases, the optimal split ratio of S-CO₂ decreases gradually. When the working conditions of the main compressor is near the supercritical point of S-CO₂, the power generation efficiency reaches the maximum. The system is more sensitive to the change of isentropic efficiency of turbine, and the power generation efficiency of the system increases by 0.7 % for every 1 % increase in isentropic efficiency. With the increase of solar irradiance and solar altitude angle, the concentrated heat collection power and efficiency of the solar thermal field increase. With the increase of solar irradiance, power generation efficiency and the output electric power of the system increases first and then decreases, peaking at 750 W/m²and 800 W/m² respectively. The optimal operating temperature of the Brayton cycle module increases from 512 ℃ at 600 W/m² to 640℃ at 750 W/m² and then drops to 610 ℃ with DNI elevation. In the process of decreasing the proportion of solar energy in the total input energy from 36 % to 16 %, the cycle efficiency of the system decreases continuously.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114018"},"PeriodicalIF":1.9,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143748234","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Characteristics of metallic uranium aerosols generated under fire conditions","authors":"Min Zhu ,&nbsp;Ming Guo ,&nbsp;Yanjun Wang ,&nbsp;Zhaoqun Shao","doi":"10.1016/j.nucengdes.2025.114021","DOIUrl":"10.1016/j.nucengdes.2025.114021","url":null,"abstract":"<div><div>Radioactive aerosol will enter the human body through the respiratory system, digestive system and other ways, seriously endangering human health. At present, there are few public reports on the generation of uranium aerosol under combustion conditions, and the experimental conditions in the existing reports differ greatly, resulting in limited reference significance. Therefore, a set of uranium aerosol experiment equipment is designed in this work, and the formation characteristics of two kinds of metallic uranium aerosol under fire conditions are studied. Thus, the information on the particle size distribution, RF (Respirable Fraction), ARF (Airborne Release Fraction) of uranium aerosols was obtained. The results indicate that particle size of two uranium aerosols exhibited log-normal and bimodal distributions, respectively, while the RF values were similar and close to 1 in both cases. The ARF values for combustion products with different compositions exhibited a high degree of similarity. Based on our experiments and literature data, the results suggests that the particle size distribution of uranium aerosols is influenced by the composition and structure of the material significantly, and the ARF is impacted by the specific surface area of the materials.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114021"},"PeriodicalIF":1.9,"publicationDate":"2025-03-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143748232","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Financial feasibility of optimizing the GA Siwabessy reactor-utilization for enhanced radioisotope production","authors":"Mudjiono ,&nbsp;Nuryanti ,&nbsp;Sudi Ariyanto ,&nbsp;Kurnia Anzhar ,&nbsp;Pini Wijayanti ,&nbsp;Yus Rusdian Akhmad ,&nbsp;Amil Mardha ,&nbsp;Djati Hoesen Salimy ,&nbsp;Jupiter Sitorus Pane ,&nbsp;Rizki Firmansyah Setya Budi ,&nbsp;Elok Satiti Amitayani ,&nbsp;Donny Nurmayady ,&nbsp;Nurlaila ,&nbsp;Ewitha Nurulhuda ,&nbsp;Nur Hasanah ,&nbsp;Imam Bastori ,&nbsp;Anis Rohanda ,&nbsp;Sufiana Solihat","doi":"10.1016/j.nucengdes.2025.114011","DOIUrl":"10.1016/j.nucengdes.2025.114011","url":null,"abstract":"<div><div>The GA Siwabessy multipurpose reactor (RSG-GAS) is a strategic facility in Indonesia, that supports various research applications and medical treatments by producing radioisotopes and radiopharmaceuticals. As the demand for critical isotopes such as I-131, Mo-99, and Ir-192 continues to grow, there is a pressing need to enhance the reactor’s capabilities to meet these requirements efficiently. This research focuses on optimizing the reactor’s utilization by prioritizing its role in isotope production and addressing operational and strategic challenges. A systematic cost-benefit analysis framework is developed to evaluate the financial feasibility of this optimization. The framework incorporates comprehensive cost components, including revitalization investments and operational expenses, while benefits are assessed in terms of increased isotope production, and economic returns. Four reactor’s irradiation channel utilization are analyzed at 15 MW and 20 MW, spanning single-product and multi-product scenarios. Results indicate that the current operational condition is financially unsustainable, while the proposed optimization scenario offer significant economic benefit. Among the configurations, dedicated I-131 production (Option 1) yields the highest financial returns, while the multi-product scenario (Option 4) balances profitability with diverse national needs. This research underscores the strategic importance of reactor revitalization in achieving Indonesia’s long-term independence in nuclear medicine and industrial applications.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114011"},"PeriodicalIF":1.9,"publicationDate":"2025-03-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143725210","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}

{"title":"Experimental study on the rewetting velocity on dry out surface due to stepwise boundary condition changes","authors":"A. Satou,&nbsp;Y. Wada,&nbsp;Y. Sibamoto","doi":"10.1016/j.nucengdes.2025.114020","DOIUrl":"10.1016/j.nucengdes.2025.114020","url":null,"abstract":"<div><div>Post-boiling transition (post-BT) heat transfer is essential for analyzing the duration of surface dryout and peak cladding temperature during abnormal transients and accidents in light water reactors. The rewetting phenomenon, in which the liquid film front propagates to the dryout surface and becomes wet again due to a decrease in heat flux or an increase in flow rate, is very important for evaluating the dryout duration. Although rewetting velocity models have been proposed mainly for reflooding processes, mechanical rewetting velocity models applicable to much higher flow and heat flux conditions than reflooding processes have been developed in recent years. However, due to the lack of an experimental database on rewetting velocities under such a wide range of thermal–hydraulic conditions, sufficient data for model development and validation do not exist. Therefore, a database on rewetting velocities caused by stepwise boundary condition changes under a wide range and multiple combination of thermal–hydraulic conditions was obtained using a single-tube experimental apparatus. Based on this database and the characteristics of rewetting velocities obtained, an empirical correlation for rewetting velocity was proposed. This correlation predicts the rewetting velocity accurately by taking the change in the mass flux of the liquid or gas phase with stepwise transients as a parameter. This suggested that the change in the mass flux of the gas or liquid phase near the liquid film front has a strong influence on the rewetting under extremely high mass flux conditions compared to the reflooding process.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114020"},"PeriodicalIF":1.9,"publicationDate":"2025-03-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143725208","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}