Annals of Nuclear Energy最新文献

{"title":"Novel active disturbance rejection control law design for nuclear reactor power level control in load following operation","authors":"Boubacar Kirgni Hamza","doi":"10.1016/j.anucene.2025.111410","DOIUrl":"10.1016/j.anucene.2025.111410","url":null,"abstract":"<div><div>Nuclear reactors are inherently complex systems characterized by significant nonlinearities. Additionally, their operational characteristics evolve over time due to factors such as power levels, aging effects, internal reactivity feedbacks, and fuel burn-up. Given this complexity and variability, nuclear reactors require advanced and highly sophisticated control strategies to ensure both optimal performance and safety throughout their operational lifespan. This paper introduces the design of a novel Active Disturbance Rejection Controller (ADRC) tailored specifically for the load-following process in nuclear reactors. The newly built controller is different from the existing ADRC and not only ensuring closed-loop asymptotic stability but also providing robustness against disturbances. The control performance of the developed ADRC law is assessed through numerical simulation where it has been compared with the traditional Linear ADRC (LADRC) and Model Free Controller (MFC) to show its superiority. It has been demonstrated that the proposed controller can achieve satisfactory tracking performance while rejecting both matched and lumped disturbances.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111410"},"PeriodicalIF":1.9,"publicationDate":"2025-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143783051","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":"The influence of mechanical parameters on the impact-sliding fretting tribocorrosion behaviors of Inconel 690 alloy","authors":"Lei Zhang ,&nbsp;Guoping Wang ,&nbsp;Meigui Yin","doi":"10.1016/j.anucene.2025.111417","DOIUrl":"10.1016/j.anucene.2025.111417","url":null,"abstract":"<div><div>Inconel 690 alloy tubes are widely used as the steam generator tubes of the pressured-water reactors of nuclear power plants. However, these tubes suffer from various hashed fretting corrosion behaviors during their service period. This study used an impact-sliding fretting corrosion tester to investigate the effects of frequency, load, and displacement on the damage dynamic response, failure mechanism, and electrochemical corrosion behaviors of Inconel 690 alloy tubes. Results showed that increased normal preload, sliding frequency, and displacement exacerbated the impact-sliding fretting surface damage, thus worsening electrochemical corrosion. The dominant tribo-corrosion damage mechanisms were abrasive wear and fatigue peeling.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111417"},"PeriodicalIF":1.9,"publicationDate":"2025-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143783048","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":"Polyvinyl and bismuth Nitrite based apron (PVABiN-Apron): Fabrication and characterization","authors":"Fahrul Bakri ,&nbsp;Paulus Lobo Gareso ,&nbsp;Ali Hamed Alomari ,&nbsp;Heryanto Heryanto ,&nbsp;Ardiansyah Ardiansyah ,&nbsp;Syarifuddin Syarifuddin ,&nbsp;Muhammad Khalis Abdul Karim ,&nbsp;Ahmad Taufiq ,&nbsp;Dahlang Tahir","doi":"10.1016/j.anucene.2025.111446","DOIUrl":"10.1016/j.anucene.2025.111446","url":null,"abstract":"<div><div>Developing PVA-based apron samples by incorporating varying concentrations of Bi(NO₃)₃ (10, 20, 30, and 40 wt%) through a mixing method has been studied. The identified chemical bonds from Fourier transform infrared (FTIR) are O-H, C-H, O=C=O, C=O, NO3⁻, and Bi-O-Bi. The crystallite size from the quantitative analysis of X-ray diffraction (XRD) shows an increase from 8.418 nm to 37.881 nm with increasing Bi(NO₃)₃ from 10 % to 40 %, respectively. We found that the best concentration is 40 wt% Bi(NO₃)₃, indicated by shielding performance’s highest linear attenuation coefficient (LAC) of 17.398 cm⁻1, mass attenuation coefficient (MAC) of 9.719 cm²/g, and effective atomic number (Zeff) of 10.943 was evaluated at 80 kVp. Furthermore, this sample exhibited the lowest half-value layer (HVL) of 0.039 cm and the tenth-value layer (TVL) of 0.132 cm, indicating exceptional shielding efficiency. Regarding mechanical properties, the 30 wt% Bi samples achieved the highest tensile strength of 3.888 N/mm² and elongation at a break of 18.445 %. These findings suggest that the 40 wt% Bi(NO₃)₃ apron sample offers a promising lead-free alternative for radiation protection, representing a crucial advancement in sustainable shielding materials. The practical implications of this research are significant, as it could lead to the development of more effective and environmentally friendly radiation protection materials.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111446"},"PeriodicalIF":1.9,"publicationDate":"2025-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143783052","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":"RSV TAPIRO and TRIGA RC-1 research reactors activities","authors":"L. Falconi,&nbsp;V. Fabrizio,&nbsp;A. Santagata","doi":"10.1016/j.anucene.2025.111409","DOIUrl":"10.1016/j.anucene.2025.111409","url":null,"abstract":"<div><div>Neutrons produced by research reactors have an important role in the development of nuclear science and technology and also in education and training on these applications.</div><div>These facilities, originally constructed during the ‘60 s and ‘70 s decades, were initially used for the national nuclear program, then their original mission was converted to host the activities correlated with the neutrons and gamma radiations.</div><div>The increasing interest in neutron radiation damage analysis, due to the very qualified energy spectrum of these types of reactors, allowed the ENEA research reactors, RC SV TAPIRO and TRIGA RC-1, to be used for different R&amp;D areas.</div><div>In this paper, the main characteristics and the most relevant applications of these two reactors carried out during their life operations have been fully described.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111409"},"PeriodicalIF":1.9,"publicationDate":"2025-04-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143767703","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":"Transmutation of long-lived fission products (LLFPs) utilizing electron Bremsstrahlung and compact subcritical assembly","authors":"Chang M. Kang ,&nbsp;Youngin Kim ,&nbsp;Jin-Kyu Kim ,&nbsp;Won-Gu Kang","doi":"10.1016/j.anucene.2025.111435","DOIUrl":"10.1016/j.anucene.2025.111435","url":null,"abstract":"<div><div>A novel approach is proposed for neutron transmutation utilizing an electron accelerator coupled with a compact subcritical system. The transmutation converter features a spherical target surrounded by a subcritical assembly composed of a moderator and low-enriched uranium in shell plates. The transmutation of six fission products, Tc-99, I-129, Cs-135, Zr-93, Se-79, and Pd-107, was investigated using electron beams with energies of 300 MeV, 30 mA and 500 MeV, 20 mA. The MCNP6.2 analyses indicate that with an electron beam of 500 MeV, 20 mA, the transmutation half-lives are all under 10 years, with 4.19 years and 5.45 years for Tc-99 and I-129, respectively, except for Zr-93, which has the longest half-life of 35 years. These transmutation half-lives represent systems with multiplication factors of approximately 0.95, and the transmutation half-life can be further reduced by raising the multiplication factor above 0.95 provided that the system’s safety at this multiplication factor is ensured.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111435"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759042","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 model predictive control method for sodium-cooled fast reactor","authors":"Shifa Wu ,&nbsp;Yunzhi Chai ,&nbsp;Jinrong Jin ,&nbsp;Areai Nuerlan ,&nbsp;Yizhe Liu ,&nbsp;Jiashuang Wan","doi":"10.1016/j.anucene.2025.111416","DOIUrl":"10.1016/j.anucene.2025.111416","url":null,"abstract":"<div><div>Sodium-cooled fast reactor (SFR) is the fourth generation reactor with inherent safety. Due to its non-dissipative characteristics, frequent power changing operation may lead to large power oscillations, which needs more advanced control methods to enhance safety and economic performance of nuclear power plants. Therefore, a Model Predictive Control (MPC) method for the SFR is proposed. The simulation model for the SFR is developed and validated. Then, the MPC method is applied to the overall control, and the MPC model in the form of state space and quadratic programming is introduced for the optimization under system constraints. To verify its performance, 100%–90 %–100 % step, 50 %–60 %–50 % step, and 50 % linear change of load transients are simulated, and compared with the traditional PID method. Results show that main parameters can quickly and stably operate without static error and with reasonable overshoot under the regulation of MPC control system.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111416"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759040","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":"Comprehensive validation of fluorine cross-sections","authors":"Tomáš Czakoj ,&nbsp;Michal Košťál ,&nbsp;Evžen Losa ,&nbsp;Vojtěch Rypar ,&nbsp;Evžen Novák ,&nbsp;Martin Schulc ,&nbsp;Bohumil Jánský ,&nbsp;Jiří Rejchrt ,&nbsp;Tomáš Peltan ,&nbsp;Adam Greš ,&nbsp;Zdeněk Matěj","doi":"10.1016/j.anucene.2025.111426","DOIUrl":"10.1016/j.anucene.2025.111426","url":null,"abstract":"<div><div>The study utilized a PTFE block with a ²⁵²Cf neutron source to measure neutron leakage flux and reaction rate distribution. Hydrogen proportional detectors and stilbene scintillators were employed for spectrum measurement. The experimental setup included various activation foils to measure reaction rates, providing a detailed analysis of neutron interactions with fluorine.</div><div>The results highlighted discrepancies between measured and calculated neutron spectra, emphasizing the need for continuous refinement of nuclear data libraries. The study compared several libraries, including ENDF/B-VIII.0, JEFF-3.3, JENDL-5, and the INDEN fluorine evaluation. It was found that all libraries underpredict measured spectrum in lower energies. Namely below 1.9 MeV in the INDEN fluorine evaluation, below 4.8 MeV in JEFF-3.3 and ENDF/B-VIII.0. JENDL-5 is out of one sigma uncertainty for almost the whole tested energy range.</div><div>Reaction rate measurements further validated the cross-sections, revealing significant discrepancies in the JENDL-5 library in lower energies. The findings underscore the importance of accurate cross-sections for reliable neutron transport simulations. The study advocates for the adoption of updated cross-sections in nuclear data libraries to enhance simulation accuracy.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111426"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759596","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":"Best-estimate plus uncertainty analysis of passive air-cooling system for a scale-down integral test facility with GOTHIC","authors":"Jian Xu ,&nbsp;Xu Han ,&nbsp;Yunyi Li ,&nbsp;Mingrui Yu ,&nbsp;Guangliang Chen ,&nbsp;Kaiyue Zeng ,&nbsp;Yisong Ma ,&nbsp;Dongliang Li","doi":"10.1016/j.anucene.2025.111387","DOIUrl":"10.1016/j.anucene.2025.111387","url":null,"abstract":"<div><div>Linglong One (ACP100) is a multifunctional modular small pressurized water reactor developed by the China National Nuclear Corporation (CNNC) with independent intellectual property rights. The Passive Containment Air-Cooling System (PAS) is one of the important safety features of ACP100, which can sustainably remove heat from the containment in the event of accidents, ensuring the integrity of the containment. In order to support the engineering application requirements of ACP100 nuclear power plant, the ACP100 containment scaled facility-PAS comprehensive performance test facility (PASE) was built. Its main purpose is to simulate large break loss of coolant accident (LBLOCA) by injecting steam into the containment, in order to verify the cooling capacity of the PAS under LBLOCA conditions. In this paper, for PASE, the best-estimate code GOTHIC was used to investigate LBLOCA, and the natural air-cooling capability of the PAS under severe accident scenarios was evaluated by the associated uncertainty assessment. The validity and usability of the GOTHIC model were verified through comparative analysis of PASE experimental data with GOTHIC calculation results, and the important thermal–hydraulic phenomena of the experimental process were also analysed. Subsequently, uncertainty analysis was conducted based on the Code Scaling, Applicability and Uncertainty (CSAU) methodology, and 12 important input uncertain parameters were selected. The 95th/95% uncertainty bands of the key output parameters were obtained based on the Wilks’ nonparametric statistics, as well as batch running of the code in conjunction with the G-Shell software package. Finally, sensitivity analyses by Spearman rank correlation coefficient were performed to identify important input uncertain contributors to the comprehensive performance of PAS.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111387"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759597","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":"Radiation emission of radioactive waste generated from 99Mo production by irradiation of uranium target in GA Siwabessy research reactor","authors":"Jaka Rachmadetin ,&nbsp;Aisyah ,&nbsp;Pungky Ayu Artiani ,&nbsp;Yuli Purwanto ,&nbsp;Mokhamad Naufal Alatas ,&nbsp;Afiq Azfar Pratama ,&nbsp;Kuat Heriyanto ,&nbsp;Dwi Luhur Ibnu Saputra ,&nbsp;Risdiyana Setiawan ,&nbsp;Parjono ,&nbsp;Kurnia Setiawan Widana ,&nbsp;Mirawaty ,&nbsp;Ratiko ,&nbsp;Wati ,&nbsp;Daddy Setiawan","doi":"10.1016/j.anucene.2025.111431","DOIUrl":"10.1016/j.anucene.2025.111431","url":null,"abstract":"<div><div>Production of medical radionuclide ⁹⁹Mo has been carried in Indonesia by irradiation of uranium target in GA Siwabessy research reactor which was started in 1996. High-enriched uranium was used as the target in the early production which was later replaced by low-enriched one in 2010 until ceased in 2014. The radioactive waste generated during the production was accumulated in the hotcells of production facility, thus the strategy of the waste management is urgently needed. The objective of this study is to determine the radiation emitted by the radioactive waste generated from the ⁹⁹Mo production by depletion calculation. The calculation was carried out using ORIGEN 2.1 code with the input of one batch of ⁹⁹Mo production using high- and low-enriched uranium targets. The major waste generated from the production were spent target capsule, radioactive fission waste, and spent gaseous apparatus which consist of cold finger and Cu fibrous column. The results of radionuclide inventory show that the spent target capsule and the radioactive fission waste are classified as intermediate-level waste. On the other hand, the spent gaseous apparatus is classified as low-level waste. Safeguards protocols must be applied to the management of radioactive fission waste because it contains almost all of nuclear material from the radionuclide production. Finally, further considerations for establishing management route for those waste are discussed.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111431"},"PeriodicalIF":1.9,"publicationDate":"2025-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143759041","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":"Novel designs and performance appraisal of non-uniformly heated annuli for heat transfer augmentation with supercritical carbon dioxide","authors":"Ashok Kumar Gond,&nbsp;Amaresh Dalal,&nbsp;Dipankar N. Basu","doi":"10.1016/j.anucene.2025.111393","DOIUrl":"10.1016/j.anucene.2025.111393","url":null,"abstract":"<div><div>Deterioration of heat transfer and possible appearance of high temperatures are common concerns in supercritical flow channels, inspiring several innovating modifications in traditional tubes. Despite the relevance of annular geometry and rod bundles in high-power applications, similar efforts are quite rare in configurations beyond the conventional channels. Present study aims at addressing this research gap by proposing and analyzing two novel designs of supercritical flow channel with variable flow areas. Annular channels with continually increasing or decreasing heater diameter within a shell, accordingly allowing axial variation in heat flux based on the local thermal conditions, facilitate converging or diverging flow paths. Five different taper angles are contemplated for either of the geometries, and numerical simulations are performed to envisage their relative performances during energy addition with supercritical carbon dioxide as the working medium. Both the designs are able to demonstrate marked improvements in overall thermalhydraulic response, with the converging duct being identified as the more preferable choice. Local heat transfer coefficient at the channel exit can be as much as 126% greater for a converging channel compared to a plain annular one, without any significant rise in pressure losses. A converging channel is also able to maintain lower temperature levels throughout the flow path, and the effects are more prominent with greater tapering. Diverging channel also records considerable gain in heat transfer, but may experience higher local temperatures and augmented pressure losses. Buoyancy effect is found to be dominant within short entrance region, while flow acceleration governs the extent of interactions in later segments. Converging duct is able to sustain temperature close to pseudocritical value within the buffer region, which can be a primary reason for its superiority. The disparity between both configurations are less significant at lower flow rates and higher powers, and the use of diverging channel can be recommended only for large power-to-flow-rate ratios, which can limit temperature ranges better than converging channel only for such specific cases.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111393"},"PeriodicalIF":1.9,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143738351","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}