Annals of Nuclear Energy最新文献_第3页

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

Treatment of molten fluoride salt-exposed graphite: Cleaning made simple

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-26 DOI: 10.1016/j.anucene.2025.111386

Y. Huang , G. Zheng , D.J. Sprouster , L.L. Snead

引用次数: 0

Impact of delayed neutrons on bifurcation and stochastic self-excited oscillations in nuclear reactors with discrete control systems

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-26 DOI: 10.1016/j.anucene.2025.111372

Amel Raked , Abdeslam Seghour , Azzedine Chafa

{"title":"Impact of delayed neutrons on bifurcation and stochastic self-excited oscillations in nuclear reactors with discrete control systems","authors":"Amel Raked , Abdeslam Seghour , Azzedine Chafa","doi":"10.1016/j.anucene.2025.111372","DOIUrl":"10.1016/j.anucene.2025.111372","url":null,"abstract":"<div><div>The present study investigates the influence of delayed neutrons on stability boundaries, chaos, and bifurcation phenomena in nuclear reactors with discrete control systems. It focuses on a point kinetics model of a reactor with a regulatory system that includes a single group of delayed neutrons and temperature feedback related to either the moderator or fuel temperature, as well as power feedback. Bifurcation diagrams are used to examine the transition to chaos, an area previously underexplored. Our research includes the development of an analytical model and detailed numerical analysis to identify stability regions and chaotic dynamics in reactor models incorporating delayed neutrons. Furthermore, we introduce innovative one-dimensional piecewise linear maps that exhibit diverse behaviors, including periodic motion, n-band chaotic attractors, exterior crisis phenomena, type I intermittency, and periods of regular motion interrupted by short quasiperiodic motion and chaotic bursts. Comparisons are drawn between models with and without delayed neutrons.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111372"},"PeriodicalIF":1.9,"publicationDate":"2025-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143706475","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

Modeling of neutron fluctuations with temperature feedback using stochastic differential equations

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-25 DOI: 10.1016/j.anucene.2025.111375

B. Dechenaux

{"title":"Modeling of neutron fluctuations with temperature feedback using stochastic differential equations","authors":"B. Dechenaux","doi":"10.1016/j.anucene.2025.111375","DOIUrl":"10.1016/j.anucene.2025.111375","url":null,"abstract":"<div><div>Neutron fluctuations, also coined zero power noise, is concerned with the study of the random fluctuations observed in the neutron population evolving in a fissile medium, due to the fundamentally intrinsic stochastic nature of the neutrons’ interactions in matter.</div><div>The canonical theoretical modeling of such fluctuations rely on the establishment of a microscopic probability balance equation, from which one can extract, with the highest precision, all of the information about the stochastic behavior of the neutron population.</div><div>An approximate yet practical scheme has been gaining in popularity in recent years. It relies on a coarse grained approach of the problem, where the evolution of the neutron population is modeled through (Itô prepoint) Stochastic Differential Equations (SDE). In this simplified scheme, the crux is to find the SDE that best approximates the fluctuations of the underlying microscopic stochastic process.</div><div>In the present work, an alternative approach to the scheme usually found in the neutronics literature is proposed. A family of SDE that best approximate the fine grain behavior of the neutron population is derived from an explicit truncation of the translation operators found in the microscopic master equation of the problem. The approach is developed over a concrete and relatively original application case, namely that of the point reactor model including mono-energetic neutrons, one group of precursors, and a temperature feedback process.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111375"},"PeriodicalIF":1.9,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143697192","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

Research on variable speed operation scheme for mobile microreactor coupled with helium gas turbine cycle

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-03-25 DOI: 10.1016/j.anucene.2025.111389

Xuyao Geng, Jie Wang

{"title":"Research on variable speed operation scheme for mobile microreactor coupled with helium gas turbine cycle","authors":"Xuyao Geng, Jie Wang","doi":"10.1016/j.anucene.2025.111389","DOIUrl":"10.1016/j.anucene.2025.111389","url":null,"abstract":"<div><div>The micro high temperature gas-cooled reactor coupled with gas turbine direct cycle has the characteristics of inherent safety, high outlet temperature and no phase change of working medium. It is a competitive mobile microreactor technology scheme. Mobile microreactors mainly operate in remote off-grid areas, and need to cope with frequent load power variations. They mainly operate in variable speed mode. While, there are few studies on the variable speed operation characteristics of mobile microreactors. In this paper, a 10MWth mobile microreactor coupled with helium gas turbine cycle (MMR-GT) is selected as research object, and the differential algebraic equations mathematical model is established. The system analysis program is developed based on Modelica language. Firstly, the characteristics of MMR-GT under constant speed and variable speed operation schemes are compared when 100pcm reactivity is inserted and the load power varies the same. In variable speed operation, the performance parameters of turbomachinery changes more obviously than that in constant speed operation. Then, the steady-state operation characteristics of MMR-GT at different rotational speed is analyzed. With the decrease of speed, the power of each component, mass flow rate and system pressure all drop rapidly. The recuperator effectiveness is higher at low flow rate, and it is increased by 15.5% when the rotational speed is reduced to 60% of the rated value. Finally, the response of MMR-GT to load power fluctuations is analyzed. Without inserting external reactivity, the decrease of load power leads to the increase of rotational speed and flow rate, the decrease of reactor outlet temperature, and the rise in reactor power due to negative feedback effect. For load power increase, the positive reactivity needs to be inserted to increase driving torque. The speed control scheme is tested for partial load power loss. It indicates that the shaft speed can be controlled at the set value through bypass valve.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111389"},"PeriodicalIF":1.9,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143697084","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