Progress in Nuclear Energy最新文献

{"title":"Upgrading the compressive strength and radiation shielding properties of high strength concrete supported with nano additives of lead monoxide and granodiorite","authors":"Islam N. Fathy ,&nbsp;Alaa A. El-Sayed ,&nbsp;Maged E. Elfakharany ,&nbsp;Alaa A. Mahmoud ,&nbsp;Mohamed A. Abouelnour ,&nbsp;Abdelhalim S. Mahmoud ,&nbsp;K.A. Mahmoud ,&nbsp;Taha A. Hanafy ,&nbsp;M.I. Sayyed ,&nbsp;Islam M. Nabil","doi":"10.1016/j.pnucene.2024.105562","DOIUrl":"10.1016/j.pnucene.2024.105562","url":null,"abstract":"<div><div>The current study aims to enhance several properties of high-strength concrete (HSC) by incorporating two distinctly classified and inherently different nanomaterials into the concrete matrix ingredients. Nano-lead monoxide (NL), known for its high density and radiation attenuation capability, and nano granodiorite powder (NG), as a promising supplementary cementitious material (SCM) with pozzolanic activity ,were individually investigated at increasing replacement ratios of cement weight up to 5%. Additionally, an optimized mix containing the optimal replacement ratios of both materials was designed to maximize the concrete shielding capacity against radiation penetration. The NL/NG concrete was analyzed using XRF, XRD, SEM, and EDX techniques. The radiation shielding assessment of the examined NL/NG-concrete mixes were evaluated using the Monte-Carlo simulation and Phy-X software. Results showed the ability of NG to improve the compressive strength of HSC, where the optimum replacement ratio was 4%, with an increase of 17.3% compared to the control mix. This improvement was at lower rates in the case of NL, where a 3% replacement ratio resulted in a 7.96% increase in compressive strength before the strength value declined at higher replacement ratios. For the other properties, increasing the replacement ratio of NL in the concrete mix leads to a delay in setting times and an increase in workability, accompanied by a decrease in consistency. On the other side, the incorporation of NG into the concrete exhibited the opposite effect on all the properties above. The combined mix of 5%NL+4%NG led to an 11.7% enhancement in the compressive strength value with improved overall concrete performance, especially its radiation shielding property. The studied NL/NG-concrete samples provide the best protection against γ-rays. Lastly, the excellent performance of the mixes of NL and NG on HSC would pave the way for their employment as radiation shielding in various nuclear and medical facilities.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105562"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141679","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":"A new iterative method based on the Q-iteration method for robust and rapid determination of concentration distribution in multicomponent separation cascades","authors":"Ruinan Wu,&nbsp;Junlu Wu,&nbsp;Enchi Liu,&nbsp;Shi Zeng","doi":"10.1016/j.pnucene.2024.105561","DOIUrl":"10.1016/j.pnucene.2024.105561","url":null,"abstract":"<div><div>Determining the concentration distribution of mixtures of multiple isotopes in separation cascades is a common task in cascade analysis and design. The robustness and efficiency of the computational method are crucial, particularly for cascade optimization. The Q-iteration method is well known for its simplicity, robustness, and rapid convergence and applies to various cascades. However, extensive experience in computation with the Q-iteration method revealed three drawbacks in certain cases: difficulties in selecting a suitable relaxation factor and appropriate update direction, as well as insufficient convergence speed. This paper analyzes the convergence properties of the Q-iteration method and its associated drawbacks and, based on the Q-iteration method, proposes a novel iterative approach, termed Minimal Residuals Q-iteration method (MR Q-iteration method), utilizing the gradient information of <span><math><mi>Q</mi></math></span> to determine the update direction and step size at a low computational cost. Three typical cascade cases, each representing one of the drawbacks, are computed to compare the performances of both the Q-iteration method and the MR Q-iteration method. The results demonstrate that the new method effectively resolves the three drawbacks and has improved robustness and faster convergence compared to the Q-iteration method, while retaining its simplicity.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105561"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141776","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":"A simple model of prompt neutron leakage self-multiplication for use in nuclear materials assay","authors":"Stephen Croft ,&nbsp;Andrea Favalli ,&nbsp;Malcolm Joyce ,&nbsp;Imre Pázsit ,&nbsp;Melissa Styth","doi":"10.1016/j.pnucene.2025.105606","DOIUrl":"10.1016/j.pnucene.2025.105606","url":null,"abstract":"<div><div>When assaying special nuclear materials using the passive neutron multiplicity counting method, due account must be taken of prompt neutron leakage self-multiplication in interpreting the various counting rates observed. Most often, in practical work, it is treated as an unknown model parameter to be determined from the experimental data. However, in a learning environment and when planning experiments, it is useful to have a straightforward means to estimate the leakage self-multiplication of a measurement item. In the present work, we develop a simple, hybrid, one energy-group, point-like source model for leakage self-multiplication, implemented with interaction probabilities calculated based on spherical and cylindrical bodies. We use published criticality tables to demonstrate the procedure. We show how the prompt neutron leakage self-multiplication may be estimated rudimentarily, including the effects of neutron scattering within the item. This treatment has considerable pedagogic value because it completes, in a similar conceptual framework, the physical point-model picture commonly used to interpret such neutron correlation counting-based measurements. It provides a straightforward quantitative physics-informed structure for making a forward prediction of the leakage self-multiplication factor of a compact non-reentrant measurement item, which otherwise is introduced as an unknown model parameter to be estimated only from experimental data with no guidance on how the value can be estimated <em>a priori</em>. The numerical sche<u>me</u> has been developed with weakly multiplying objects in mind because they are typical of the kind of items measured by thermal-neutron well-counters for nuclear safeguards accountancy and nonproliferation verification purposes. Another potential use is for the assay of measurement items of known geometry and composition where the prompt neutron self-leakage multiplication can be estimated using the simple model developed, thereby allowing the (α,n) production rate to be treated as the unknown in the practical solution (or inversion) of the usual point-model coincidence equations.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105606"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141803","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":"Study on internal flow characteristics of reactor coolant pump under non-uniform inflow","authors":"Yun Long,&nbsp;Yuan Xu,&nbsp;Xi'an Guo,&nbsp;Mingyu Zhang","doi":"10.1016/j.pnucene.2025.105628","DOIUrl":"10.1016/j.pnucene.2025.105628","url":null,"abstract":"<div><div>This study explored the complexity of internal flow patterns in a reactor coolant pump (RCP) facing non-uniform inflow conditions. Utilizing CFD simulations, we analyzed the flow behavior under non-uniform inlet conditions simulated by a steam generator and compared it with flows under standard straight pipe inlets. The examination covered five main computational areas: the inlet, the rotating impeller, the stationary diffuser, the casing, and the outlet extension. By examining the transient evolution of the pump's primary flow components under varying inflow conditions, the study exposed the impact of non-uniform inflow on the pump's internal flow field. It was observed that non-uniform inflow, particularly under the simulated conditions of the steam generator, significantly influences the velocity and pressure distributions within the impeller and diffuser, consequently affecting the pump's performance by reducing flow stability and energy conversion efficiency. Additionally, the study established grid independence, ensuring the accuracy and reliability of the numerical simulation results. These findings offer vital scientific insights for the design and operation of RCPs and enhance the prediction and optimization of real pump performance through precise flow field simulations that reflect actual inflow conditions.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105628"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140995","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":"Anti-carburization strategies for superalloys Inconel 617 and Incoloy 800H during service in VHTR coolant: Pre-oxidation and continuous oxidation","authors":"Bin Du,&nbsp;Huang Zhang,&nbsp;Jiahao Chang,&nbsp;Penghui Xiao,&nbsp;Baozhi Wu,&nbsp;Huaqiang Yin,&nbsp;Xuedong He,&nbsp;Tao Ma","doi":"10.1016/j.pnucene.2025.105640","DOIUrl":"10.1016/j.pnucene.2025.105640","url":null,"abstract":"<div><div>This study investigates the effects of pre-oxidation and continuous oxidation on the corrosion behavior and plasticity of Inconel 617 and Incoloy 800H in a helium atmosphere containing 400 ppm methane at 950 °C. The results show that, without protective measures, both Inconel 617 and Incoloy 800H experienced severe internal carburization, leading to a significant reduction in plasticity (617: 44%→21%, 800H: 42%→21.7%). After pre-oxidation in air at 950 °C for 10 h, a Cr-oxide layer formed on both alloys. However, the oxide layer was porous and failed to effectively prevent internal carburization. Furthermore, the oxide layer promoted the initiation and propagation of surface cracks, further reducing alloy plasticity (617: 44%→2.3%, 800H: 42%→18.3%). Continuous oxidation (introducing 200 ppm O₂ in helium) effectively mitigates the issue of reduced plasticity in the alloy (617: 44%→39.2%, 800H: 42%→40.7%). This is because continuous oxidation promotes the formation of a denser oxide layer, which hinders the inward diffusion of carbon atoms. Additionally, the SiO₂ generated during continuous oxidation reduces the adhesion between the oxide layer and the substrate, preventing the alloy matrix from being affected by crack propagation in the oxide layer during plastic deformation. In conclusion, continuous oxidation is an effective strategy for preventing carburization of alloys in VHTR environments.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105640"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140999","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":"Development of source term estimation model using Kalman filter technique and its evaluation against reversal method","authors":"Dipan Kundu,&nbsp;Shanu Karmakar,&nbsp;C.V. Srinivas,&nbsp;V. Gopalakrishnan,&nbsp;B. Venkatraman","doi":"10.1016/j.pnucene.2025.105618","DOIUrl":"10.1016/j.pnucene.2025.105618","url":null,"abstract":"<div><div>A Kalman Filter (KF) algorithm is developed for radionuclide source term estimation based on real-time gamma dose rate and meteorological data. The algorithm uses Gaussian Plume Model (GPM) with nonlinear build-up factor in dose rate model to eliminate one source of uncertainty in source term estimation. The estimated release rate from the KF algorithm is compared against GPM reversal technique and tested against routine Ar-41 release data under dynamic meteorological condition. Several simulations are performed over two days periods in the months of February, March and April 2021 representing winter, summer and pre-monsoon weather conditions at Kalpakkam site. Results showed that the mean bias in KF predicted source term (bias ∼0.09 GBq.s⁻¹) is 3 times lesser compared to GPM reversal method (bias ∼0.32 GBq.s⁻¹). In KF algorithm a tuning based method is used for estimation of noise covariance matrix. The noise filtering/reduction methodology in KF algorithm reduces the fluctuations in KF predicted release rate (RMSE ∼0.13 GBq.s⁻¹) by 3 times compared to GPM reversal method (RMSE ∼0.37 GBq.s⁻¹). The correlation coefficient of KF estimated source term (CC ∼0.57) is 6 times more compared to the GPM reversal method (CC ∼0.10). Though both methods (KF and GPM reversal) could capture the observed dose rate variations with correlation coefficient of ∼0.65, on an average the predicted release rate is 2.0 and 4.5 times more using KF and GPM reversal techniques respectively compared to actual data. Overall, the KF estimates more reasonable and accurate source term compared to the GPM reversal method.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105618"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140932","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":"Adsorptive removal of Sr(II) from aqueous solution by xanthate modified chitosan","authors":"Bowen Xu ,&nbsp;Huiyu Tian ,&nbsp;Jianbo Chen ,&nbsp;Lifeng Wei ,&nbsp;Kai Wang ,&nbsp;Jianlong Wang","doi":"10.1016/j.pnucene.2025.105621","DOIUrl":"10.1016/j.pnucene.2025.105621","url":null,"abstract":"<div><div>In this study, xantahted chitosan (CTS-X) was synthesized through a simple one-step preparation method, the analysis results of XPS and FT-IR spectra confirmed the successful introduction of xanthate. The specific surface area of CTS-X was higher than original chitosan, and the pore structure was relatively simple. CTS-X exhibited excellent adsorption performance for Sr(II). The adsorption rate of Sr(II) was fast, and the rate-limiting step was extra diffusion process. The maximum adsorption capacity was 58.36 mg g⁻¹, calculated by D-R isotherm model, which was higher than most chitosan-based adsorbents. The main adsorption sites were hydroxyl groups and xanthates. Due to simple preparation and excellent adsorption performance, CTS-X has potential in application for radionuclide separation from radioactive wastewater.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105621"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140934","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":"Development and evaluation of a two-dimensional neutron diffusion model of a small modular heat-only reactor TEPLATOR using COMSOL","authors":"Dipanjan Ray ,&nbsp;Martin Lovecký ,&nbsp;Jiří Závorka ,&nbsp;Radek Škoda","doi":"10.1016/j.pnucene.2025.105642","DOIUrl":"10.1016/j.pnucene.2025.105642","url":null,"abstract":"<div><div>TEPLATOR, a collaborative innovation between researchers from the University of West Bohemia (UWB) and Czech Technical University (CTU), represents a promising solution for environmentally sustainable energy demands. This small modular heat-only reactor features a heavy water-cooled and heavy water-moderated pressure channel design, offering an alternative to fossil fuel-dependent heating and cooling plants, thereby reducing environmental impact and pollution. This article outlines the initial steps in developing a detailed neutron diffusion model for the TEPLATOR core using COMSOL Multiphysics software. The study focuses on developing and evaluating a two-group steady-state neutron diffusion model for the two-dimensional reactor geometry to analyze spatial neutronic dynamics under various control rod positions. Neutronic parameters were computed using the Serpent Monte Carlo neutron transport code and integrated into the diffusion model as multi-group constants. Calculations were conducted for the Beginning-of-Cycle (BOC) scenario. The obtained values of effective multiplication factor (<span><math><mrow><msub><mi>k</mi><mrow><mi>e</mi><mi>f</mi><mi>f</mi></mrow></msub></mrow></math></span>) from both the developed COMSOL diffusion model and Serpent codes remain consistent, with differences ranging from 242 pcm to 643 pcm across different control rod position scenarios. Additionally, the computational time of the developed diffusion model is significantly shorter than that of the Serpent code. Furthermore, the effectiveness of the diffusion model for practical design investigations and sensitivity analyses of the TEPLATOR reactor core is demonstrated by presenting steady-state neutron flux and power distribution calculated by the diffusion model, which was compared with Serpent code computations.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105642"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141002","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":"Development and assessment of an additional inertia force model for one-dimensional nuclear system analysis code under ocean conditions","authors":"Jiayue Chen,&nbsp;Zhihong Liu,&nbsp;Wanai Li","doi":"10.1016/j.pnucene.2024.105597","DOIUrl":"10.1016/j.pnucene.2024.105597","url":null,"abstract":"<div><div>The accurate evaluation of system thermal hydraulic oscillations under ocean conditions is an important and challenging issue for marine nuclear reactor system. In this paper, an additional inertia force model accounting for effects of the heaving, yawing, rolling and complex movements under ocean conditions were established. This model was incorporated into the two-fluid momentum equation as an additional inertia body force. A series of numerical tests devised with analytical solutions were simulated for verification. The comparison results show that the model can accurately predict the translational acceleration, as well as gravity, centrifugal and Euler forces individually. However, deviations are observed with large amplitude-to-period ratios in rotating scenarios. The model further demonstrates its modeling capabilities by alternating the flow directions and varying the position of rotation center and the direction of rotation axis. Additionally, experimental data from a natural circulation loop under rolling motion were used to validate the proposed model, showing that it can effectively predict the oscillation amplitude and period of the natural circulation oscillations, even under irregular rolling conditions during the initial phase of rolling onset.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105597"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141592","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":"Study on coupled heat transfer characteristics and performance optimization for a helical coil heat exchanger in the lead-cooled fast reactor","authors":"Zhenxin Lei,&nbsp;Liangxing Li,&nbsp;Haoxiang Zhao,&nbsp;Shang Shi,&nbsp;Zutao Xiang,&nbsp;Xiangyang Xu","doi":"10.1016/j.pnucene.2024.105583","DOIUrl":"10.1016/j.pnucene.2024.105583","url":null,"abstract":"<div><div>Helical coil heat exchangers (HCHEs) are extensively applied in thermal engineering, petrochemical engineering, nuclear reactors and refrigeration engineering etc. due to the remarkable benefits of high heat transfer efficiency with compact structures. The coupled heat transfer characteristics and performance optimization of HCHE are paramount for long-lasting operational safety of the miniaturized lead-cooled fast reactors (LFRs), especially using liquid lead and supercritical carbon dioxide (s-CO₂) as the working mediums. The present work conducts a numerical study on the flow and heat transfer characteristics of lead and s-CO₂ in HCHE under different mass flow and inlet temperature. Then the Non-dominated Sorting Genetic Algorithm-II (NSGA-II) is employed to carry out the geometry optimization with Performance Evaluation Criterion (<em>PEC</em>) and heat transfer area (HTA) as the objective functions. The results indicates that the coupled heat transfer performance is primarily affected by the mass flow of s-CO₂, the mass flow of lead and the inlet temperature of lead. When the mass flow of s-CO₂ increases by 52%, the overall heat transfer coefficient (HTC) of helically coiled tubes increases by 21%. To improve the comprehensive performance, three structural parameters of HCHE that should be preferred in the process of optimization design are tube-outer diameter, the number of layers and the number of tubes on the first layer.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105583"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141634","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}