Annals of Nuclear Energy最新文献_第3页

Attenuation ability of tungsten and cadmium-reinforced polymeric materials as protective shields against gamma radiation and thermal neutrons

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-28 DOI: 10.1016/j.anucene.2025.111412

Dalal Abdullah Aloraini , W.A. Abu‑raia , Aly Saeed

引用次数: 0

Implementation of dynamic Monte Carlo simulation using IMPC-NP for transient analysis of subcritical reactor driven by external neutron source

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-28 DOI: 10.1016/j.anucene.2025.111415

Peng Fang , Yanling Zhu , Feng Zhou , Qiuying Liang , Shijie Du , Yongwei Yang , Lei Yang

{"title":"Implementation of dynamic Monte Carlo simulation using IMPC-NP for transient analysis of subcritical reactor driven by external neutron source","authors":"Peng Fang , Yanling Zhu , Feng Zhou , Qiuying Liang , Shijie Du , Yongwei Yang , Lei Yang","doi":"10.1016/j.anucene.2025.111415","DOIUrl":"10.1016/j.anucene.2025.111415","url":null,"abstract":"<div><div>In order to meet the requirements of neutron dynamics analysis for China’s initiating Accelerator Driven System (CiADS), we have implemented the calculation function of neutron kinetic parameters (<em>β</em><sub>eff</sub> and <em>Λ</em><sub>eff</sub>) and the Dynamic Monte Carlo transient analysis function in the Monte Carlo code IMPC-NP. Most importantly, based on this, we have implemented a dynamic transient analysis function with external neutron sources. This is the first simulation using dynamic Monte Carlo code with external neutron sources. On the basis of verifying the reliability of the code, this article simulated the external neutrons under subcritical conditions and obtained the flux variation law under specific conditions. This code can simulate the transient evolution of neutrons in ADS core under different external neutron souces strength and distributions in the future, providing important reference data for beam control of accelerators in ADS facility. This code tool has significant application significance.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111415"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143724804","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}

引用次数: 0

Enhancement on optical properties and radiation shielding performance of new formulation zinc modified boro-tellurite glasses

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-28 DOI: 10.1016/j.anucene.2025.111411

Aliyu Sani , Mohd Hafiz Mohd Zaid , Khamirul Amin Matori , Muhammad Khalis Abdul Karim , Loh Zhi Wei

{"title":"Enhancement on optical properties and radiation shielding performance of new formulation zinc modified boro-tellurite glasses","authors":"Aliyu Sani , Mohd Hafiz Mohd Zaid , Khamirul Amin Matori , Muhammad Khalis Abdul Karim , Loh Zhi Wei","doi":"10.1016/j.anucene.2025.111411","DOIUrl":"10.1016/j.anucene.2025.111411","url":null,"abstract":"<div><div>The main goal of this research is to determine the fundamental characteristics of <em>x</em>ZnO − 30B<sub>2</sub>O<sub>3</sub>−(70-<em>x</em>)TeO<sub>2</sub> glass system that can be used as radiation shielding. Ultrasonic analysis and UV–Vis results show Urbach energy ranges from 1.071 to 0.737 S<sup>-1</sup>, whereas the direct and indirect optical band gaps increase between 3.194 and 3.270 and 2.22 to 2.64 eV, respectively. The density of the glasses varies between 4.25 and 4.04 g/cm<sup>3</sup>. As the ZnO concentration increases, all elastic moduli decrease as well as microhardness from 5.63 to 3.92 GPa and Poisson’s ratio from 0.26 to 0.24 based on the results from ultrasonic measurement. The refractive index of a glass changes from 1.98 to 2.02, their molar volume decreases from 32.77 to 28.91 cm<sup>3</sup>/mol, and molar weight decreases from 132.61 to 116.96 g/mol, whereas oxygen molar volume ranges from 12.1 to 9.73, and the oxygen packing density changes from 2.3 to 2.1 mol/cm<sup>3</sup>. Electronegativity, Optical Polarizability, and Basicity ranging from 0.86 to 0.87, 2.73 to 2.71, and 1.27 to 1.26, respectively. All the radiation factors for the robust glass system were calculated using the Phy-X/PSD programming.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111411"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143724805","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}

引用次数: 0

A boron concentration maneuvering control algorithm for reactivity management during transients in VVER-1000 nuclear power units

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-28 DOI: 10.1016/j.anucene.2025.111381

Ahmed E. Salman , Hassan E. Gomaa

{"title":"A boron concentration maneuvering control algorithm for reactivity management during transients in VVER-1000 nuclear power units","authors":"Ahmed E. Salman , Hassan E. Gomaa","doi":"10.1016/j.anucene.2025.111381","DOIUrl":"10.1016/j.anucene.2025.111381","url":null,"abstract":"<div><div>Effective reactivity management is paramount for the safe and efficient operation of VVER-1000 reactors. A high-fidelity dynamic model is developed for boron control based on point kinetic equations, which capture the complex reactor kinetics, boron dynamics, and associated feedback systems governing the reactor’s behavior. The algorithm utilized a Proportional–Integral–Derivative controller optimized via Sequential Quadratic Programming (PID-SQP controller) to optimize boron maneuvering and compensate for external disturbances successfully. Step disturbances are applied to reactor inlet temperature at different boration/dilution rates to assess the algorithm’s resilience. The controller successfully regulated the power but exhibited different characteristics regarding overshoot, undershoot, smoothness of the change, and settling time. A statistical-based optimization analysis of the responses is conducted to determine the optimal levels for smooth and fast responses. The results exhibit enhanced stability, faster response times, and reduced boron overshoot transients. A dynamic optimization plot is constructed to figure out the boration/dilution rate yielding the highest composite desirability index.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111381"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143715635","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}

引用次数: 0

Fast, accurate numerical evaluation of incomplete Planck integrals

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-27 DOI: 10.1016/j.anucene.2025.111374

Whit Lewis, Ryan G. McClarren

引用次数: 0

Development of a start-up core for sustaining rotational fuel shuffling strategy for a nitride fueled lead-cooled fast reactor

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-27 DOI: 10.1016/j.anucene.2025.111379

Alexandru Catalin Stafie, Toru Obara

{"title":"Development of a start-up core for sustaining rotational fuel shuffling strategy for a nitride fueled lead-cooled fast reactor","authors":"Alexandru Catalin Stafie, Toru Obara","doi":"10.1016/j.anucene.2025.111379","DOIUrl":"10.1016/j.anucene.2025.111379","url":null,"abstract":"<div><div>This study investigates a start-up core design for a lead-cooled fast reactor employing a Rotational Fuel-shuffling Breed-and-Burn (RFBB) strategy using High-Assay Low-Enriched Uranium (HALEU) nitride fuel. Based on the Westinghouse Lead-cooled Fast Reactor, the reactor can achieve and maintain criticality using natural uranium as feed fuel for a refueling interval of 1050 EFPD. Analysis indicates an equilibrium discharge burnup of <span><math><mrow><mo>∼</mo><mspace></mspace><mn>230</mn><mspace></mspace><mi>MWd/kgHM</mi></mrow></math></span>. The refueling strategy gradually replaces HALEU fuel with natural uranium assemblies, ensuring stable power profiles during the transition cycles. The reactivity control system can insert at least <span><math><mrow><mo>∼</mo><mn>15</mn><mspace></mspace><mtext>$</mtext></mrow></math></span> negative reactivity. Thermohydraulic assessments confirm effective heat removal, with peak fuel temperatures within operational limits. The study addresses proliferation risks from weapons-grade plutonium generation by proposing strategies for fuel reutilization and fuel assembly optimization. The study confirms the feasibility of the start-up core to sustain the RFBB mode while suggesting the potential for further optimization to control excess reactivity and enhance proliferation resistance.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111379"},"PeriodicalIF":1.9,"publicationDate":"2025-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143706362","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}

引用次数: 0

Evaluation of thermal scattering law and cross sections for liquid hydrogen fluoride

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-27 DOI: 10.1016/j.anucene.2025.111403

T. Ahmed, N.C. Fleming, A.I. Hawari

{"title":"Evaluation of thermal scattering law and cross sections for liquid hydrogen fluoride","authors":"T. Ahmed, N.C. Fleming, A.I. Hawari","doi":"10.1016/j.anucene.2025.111403","DOIUrl":"10.1016/j.anucene.2025.111403","url":null,"abstract":"<div><div>Liquid anhydrous hydrogen fluoride (HF) is a material commonly used in fuel manufacturing and processing, and as a result it is of particular interest for criticality safety applications. In order to capture the thermal scattering impacts from this hydrogenous material, accurate thermal scattering law (TSL, i.e. S(α,β)) libraries were developed. Using classical molecular dynamics (MD) simulation of the liquid HF system, a parametrized three-site model was developed in the GROMACS MD code to accurately represent the hydrogen bond and capture the liquid’s interatomic structure. This computational model (referenced as the NCSU HF model) was constructed with a massless charge to capture the hydrogen bonds between molecules. The accuracy of the NCSU HF model was verified by comparing its predictions of various HF properties with experimental data for the hydrogen and fluorine bond length, density, potential energy, dipole moment, and diffusion coefficient. From this model, the primary inputs of the phonon density of states (DOS) and liquid diffusion properties were derived for use in the Full Law Analysis Scattering System Hub (<em>FLASSH</em>) to evaluate the TSL for both H(HF) and F(HF). These TSL libraries were benchmarked using the ICSBEP HEU-SOL-THERM-039 critical assembly benchmark, showing notable improvement on the order of 1170 pcm. The libraries generated in this work have been accepted in the ENDF/B-VIII.1 nuclear data release.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111403"},"PeriodicalIF":1.9,"publicationDate":"2025-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143705540","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}

引用次数: 0

Neural network-based prediction of decommissioning costs for SMRs

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-27 DOI: 10.1016/j.anucene.2025.111392

Balázs Kocsis

引用次数: 0

Neutronic assessment of stable salt reactor with reprocessed fuels

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-26 DOI: 10.1016/j.anucene.2025.111383

Natália Gonçalves , Clarysson A.M. Silva , María Lorduy-Alós , Sergio Gallardo , Claubia Pereira , Gumersindo Verdú

{"title":"Neutronic assessment of stable salt reactor with reprocessed fuels","authors":"Natália Gonçalves , Clarysson A.M. Silva , María Lorduy-Alós , Sergio Gallardo , Claubia Pereira , Gumersindo Verdú","doi":"10.1016/j.anucene.2025.111383","DOIUrl":"10.1016/j.anucene.2025.111383","url":null,"abstract":"<div><div>As global energy demand is projected to increase significantly, identifying sustainable and efficient energy solutions is imperative. Small Modular Reactors (SMRs) utilizing Molten Salt Reactor (MSR) technology offer a viable approach, providing flexibility, efficiency, and reduced radioactive waste. This study examines the Stable Salt Reactor (SSR-W300), focusing on the neutronic behavior of various fuel compositions derived from PUREX (Plutonium–Uranium Redox Extraction) and UREX+ (Uranium Extraction Plus) reprocessing. The analysis utilizes the MCNP6 code to evaluate the impact of different reflector thicknesses on neutron parameters and the performance of fuels. It is determined that a 50 cm reflector thickness optimizes neutron economy while managing costs. Furthermore, comparisons of PUREX-derived fuel with UREX + fuels, which include minor actinides, reveal that UREX + fuels produce a flatter neutron flux profile and exhibit improved criticality over extended periods. The findings suggest that extending the refueling interval beyond the conventional 6 months to 8 months could enhance reactor performance. This study underscores the potential of Stable Salt Reactors (SSRs) to address growing energy demands through sustainable and efficient means.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111383"},"PeriodicalIF":1.9,"publicationDate":"2025-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143704540","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}

引用次数: 0

IVMR modelling with transient effects during molten pool formation and stabilization – Outcomes from models’ comparison performed in the IAEA CRP J46002

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-26 DOI: 10.1016/j.anucene.2025.111365

Laure Carénini , Muhammad Abu Bakar , Aleksandr Filippov , Romain Le Tellier , Ivan Melnikov , Peter Pandazis , Mindaugas Valincius , Zijie Wu , Yapei Zhang

{"title":"IVMR modelling with transient effects during molten pool formation and stabilization – Outcomes from models’ comparison performed in the IAEA CRP J46002","authors":"Laure Carénini , Muhammad Abu Bakar , Aleksandr Filippov , Romain Le Tellier , Ivan Melnikov , Peter Pandazis , Mindaugas Valincius , Zijie Wu , Yapei Zhang","doi":"10.1016/j.anucene.2025.111365","DOIUrl":"10.1016/j.anucene.2025.111365","url":null,"abstract":"<div><div>In 2020, the International Atomic Energy Agency (IAEA) has started the 4-year Coordinated Research Project (CRP) on In-Vessel Melt Retention (IVMR) with the main objective to harmonize the international understanding of the scientific and technological bases underpinning crucial parts of the safety demonstration of this Severe Accident (SA) management strategy. This strategy consists in maintaining the degraded reactor core (corium) within the vessel by ensuring its cooling thanks to cavity flooding and power extraction through the vessel wall.</div><div>In the scope of this CRP, analytical benchmarks were performed focusing on different reactor designs. Among them, a generic 1000MWe PWR design benchmark was set up with a different objective compared to those dedicated to a given scenario and reactor. Its main purpose was to allow detailed comparison of models implemented in capable codes (either integral SA code or dedicated code) based on prescribed and simplified configurations. This paper presents the work done and achievements obtained within this benchmark. Different cases, corresponding to different corium configurations and boundary conditions, were developed with increasing complexity. In total, eight benchmarks are studied covering molten pool formation from solid particles, progressive corium relocation to the lower plenum, progressive molten steel incorporation, vessel wall ablation and possible stratification inversion. Together, they form an efficient and useful tool to better understand IVMR results and code capabilities or limitations. State of codes performance and remaining issues are discussed, focusing mainly on configurations involving progressive molten material arrival in the lower plenum.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111365"},"PeriodicalIF":1.9,"publicationDate":"2025-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143704541","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}

引用次数: 0