Journal of Nuclear Engineering and Radiation Science最新文献_第8页

Development of Analysis Tools for Heat Pipes Used in the Core Cooling of Small Modular Reactors: Potassium Property Correlations 小型模块堆堆芯冷却用热管分析工具的发展:钾的性质相关性

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-06-16 DOI: 10.1115/1.4062752

T. Beuthe, Hooman Jazebizadeh, Aleksandar Vasić, A. Pegarkov, T. Kaya, H. Zahlan

引用次数: 0

A Novel Algorithm for CAD to CSG Conversion in McCAD McCAD中CAD到CSG转换的新算法

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Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-06-15 DOI: 10.3390/jne4020031

M. Harb, D. Leichtle, U. Fischer

引用次数: 0

Reliability Assessment of NPP Safety Class Equipment Considering the Manufacturing Quality Assurance Process 考虑制造质量保证过程的核电厂安全级设备可靠性评估

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-06-02 DOI: 10.3390/jne4020030

M. Khalaquzzaman, Seung Jun Lee, Muhammed Mufazzal Hossen

{"title":"Reliability Assessment of NPP Safety Class Equipment Considering the Manufacturing Quality Assurance Process","authors":"M. Khalaquzzaman, Seung Jun Lee, Muhammed Mufazzal Hossen","doi":"10.3390/jne4020030","DOIUrl":"https://doi.org/10.3390/jne4020030","url":null,"abstract":"Quality and safety are intensely related and go hand in hand. Quality of the safety-grade equipment is very important for the safety of a nuclear power plant (NPP) and achieving production goals. During manufacturing of plant components or equipment, deviation from the design might occur at different stages of manufacturing for various reasons, such as a lack of skilled manpower, deviation of materials, human errors, malfunction of equipment, violation of manufacturing procedure, etc. These deviations can be assessed cautiously and taken into consideration in the final safety analysis report (FSAR) before issuing an operating license. In this paper, we propose a Bayesian belief network for quality assessment of safety class equipment of NPPs with a few examples. The proposed procedure is a holistic approach for estimation of equipment failure probability considering manufacturing deviations and errors. Case studies for safety-class dry transformers and reactor pressurizers employing the proposed method are also presented in this article. This study provides insights for probabilistic safety assessment engineers and nuclear plant regulators for improved assessment of NPP safety.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2023-06-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89622535","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Application of Np–Am Mixture in Production of 238Pu in a VVER-1000 Reactor and the Reactivity Effect Caused by Loss-of-Coolant Accident in the Central Np–Am Fuel Assembly Np-Am混合物在VVER-1000反应堆238Pu生产中的应用及中央Np-Am燃料组件冷却剂丢失事故引起的反应性影响

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Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-06-01 DOI: 10.3390/jne4020029

A. Shmelev, N. Geraskin, V. Apse, V. Glebov, E. Kulikov, A. Krasnoborodko

引用次数: 0

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code 基于蒙特卡罗代码的针式超临界二氧化碳反应器慢化剂优化设计与分析

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-05-31 DOI: 10.1115/1.4056772

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu

{"title":"Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code","authors":"Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu","doi":"10.1115/1.4056772","DOIUrl":"https://doi.org/10.1115/1.4056772","url":null,"abstract":"Abstract This study analyzed an yttrium hydride (YH2) moderated supercritical carbon dioxide cooled reactor loaded with pin-type, beryllium oxide diluted oxide fuel elements to reduce the critical enrichment. The impact of the YH2 on the coolant void reactivity was studied along with a moderator zoning scheme to flatten the radial power distribution. The YH2 was added as hexagonal moderating rods at the center of the fuel assemblies. The core was modeled using the continuous-energy Reactor Monte Carlo code (RMC) with the on-the-fly cross sections treatment. The results showed that the YH2 moderator increased the thermal fission and reduced the critical enrichment of the core with the same diluent volume fraction by more than 30%. The YH2 moderator significantly softened the neutron energy spectrum and reduced the neutron leakage upon core voiding, resulting in both a weaker positive spectral reactivity feedback and a weaker negative leakage reactivity feedback during core depressurization. For an UO2-loaded core, the YH2 gave a lower negative coolant void reactivity, while for a mixed oxide fuel (MOX)-loaded core with diluent volume fractions smaller than 35%, the spectral feedback was more important and the YH2 strongly reduced the positive coolant void reactivity to less than $1. Arranging the YH2 in the peripheral assemblies reduced the radial power peaking factor to 1.319. The study shows that the YH2 moderator can reduce the critical enrichment, make the core less sensitive to voiding, and can flatten the radial power distribution of a single-enrichment core through moderator zoning.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135195823","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Fabrication Aspects and Performance Characterization of α-Al2O3/ALPO4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications 高温液态金属用α-Al2O3/ALPO4夹层结构流道嵌套和涂层的制备方法及性能表征

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-05-27 DOI: 10.1115/1.4062646

A. Saraswat, R. Bhattacharyay, P. Chaudhuri, S. Gedupudi

{"title":"Fabrication Aspects and Performance Characterization of α-Al2O3/ALPO4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications","authors":"A. Saraswat, R. Bhattacharyay, P. Chaudhuri, S. Gedupudi","doi":"10.1115/1.4062646","DOIUrl":"https://doi.org/10.1115/1.4062646","url":null,"abstract":"\u0000 Liquid metals (LMs) exhibit several key characteristics justifying their utilization as coolants/breeders for nuclear fusion reactors and advanced fission reactors. In a fusion reactor, LMs confront a large flow retarding MHD force, imposing significant demands on pumping power and designs of ancillary systems. Corrosion of structural materials and coolant chemistry control are vital issues common to both fusion and fission reactors employing liquid lead (Pb) and its alloys. To address these concerns, technological solutions such as Flow Channel Inserts and corrosion resistant coatings are being investigated to provide a chemical/electrical isolation between LM and structural material. In this study, three prototype geometries (circular, square and 90 bend) of steel-insulator-steel FCIs are fabricated and an electrical insulation characterization is performed over a temperature range of 100C - 600C. Welding trials and pressure tests are performed to validate the electrical and mechanical integrity over typical fusion reactor operational regime. This paper presents detailed fabrication aspects along with quantitative estimations of insulation filling density, electrical insulation performance and, for the first time, a systematic study of insulation degradation owing to combined effects of TIG welding, pressure and machining operations. Critical details derived from metallurgical examinations and destructive tests are also presented. From implementation perspective towards LFRs, a feasibility assessment of a-Al2O3/AlPO4 thin film coating deposition on planar and non-planar substrates is performed followed by its mechanical characterizations. Detailed metallurgical analyses are presented to assess Pb ingress after 700 hour exposure to molten Pb alloy.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2023-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77085142","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Comparative Maps of Safety Features for Fission and Fusion Reactors 裂变和聚变反应堆安全特征比较图

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-05-27 DOI: 10.1115/1.4062643

Tu Nguyen, E. Patterson, Richard J. K. Taylor, Y. Tseng, C. Waldon

引用次数: 0

Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production 小型模块化反应堆:作为新兴核电技术的机遇与挑战

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-05-27 DOI: 10.1115/1.4062644

L. Ghimire, E. Waller

{"title":"Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production","authors":"L. Ghimire, E. Waller","doi":"10.1115/1.4062644","DOIUrl":"https://doi.org/10.1115/1.4062644","url":null,"abstract":"\u0000 Small Modular Reactors (SMRs) have gained international attention due to their modular design, small footprint, and lower capital costs for research, development, and construction compared to conventional reactors. Many types of SMRs are being developed in different countries, and regulatory agencies are working on a robust and “harmonized” SMR regulatory framework to ensure safety and protect the environment. However, there are still many details that need to be understood, such as nuclear fuel behavior at high pressures and temperatures (1000 °C), types and levels of radiation exposure during normal operations and accidents, types and volume of nuclear waste, and their proper storage and disposal. Moreover, SMRs' modular design and small size make them suitable for remote locations, such as the Canadian Arctic. However, before introducing this technology, a detailed study of the arctic soil (permafrost) is needed in the context of changing climate. Probabilistic risk assessment (PRA) is a crucial methodology for assessing the safety and reliability of nuclear power plants. Due to multi-module nature of SMRs, cross-unit interactions ( multi-module effects) need to be evaluated as part of the total plant safety assessment. Additionally, given the nature of fuels (low-enriched uranium) and the possible remote location with minimal technical staff, nuclear materials may have a higher probability of diversion. Therefore, nuclear safeguards and material accountancy are essential to prevent nuclear proliferation. This paper discusses the benefits and challenges of deploying different SMR technologies for electricity generation and other applications.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2023-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87101671","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Main Parameters Influencing The Level Of Labile Contamination And The Removal Factor 影响不稳定污染水平及去除率的主要参数

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-05-18 DOI: 10.1115/1.4062550

Pierrick Agullo, A. Gossard, G. Ranchoux, E. Porcheron, Fabrice Petitot

{"title":"Main Parameters Influencing The Level Of Labile Contamination And The Removal Factor","authors":"Pierrick Agullo, A. Gossard, G. Ranchoux, E. Porcheron, Fabrice Petitot","doi":"10.1115/1.4062550","DOIUrl":"https://doi.org/10.1115/1.4062550","url":null,"abstract":"\u0000 Several nuclear facilities are currently dismantling in France, namely on CEA's and EDF's sites. The whole decommissioning and dismantling, cutting operations and nuclear waste management can significantly affect worker risks. In this context, this work aims to better assess the internal exposure risks for operations where removal factor and airborne release factor play an essential part in the uncertainties. For that purpose, developing a new method for assessing the risk of internal exposure is necessary to optimize the choice of Personal Protective Equipment during nuclear dismantling.\u0000 Based on a bibliographic study and feedback, we identified most of the forces and parameters that influence labile contamination removal and particles resuspension. Their high number forced us to highlight the most relevant ones regarding data from the bibliography and worksite reality. Thus, the role of the drying temperature, relative humidity, roughness of the contaminated surface and the swiping pressure were particularly studied on the assessment of the labile contamination and the removal factor. For that, we performed successive wiping operations with cotton wipes on surface on which a simulated labile contamination was deposited to estimate the influence of different parameters on the total labile contamination and the removal factor. Thus, we have highlighted the high influence of roughness on these latter compare to the other identified parameters.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2023-05-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76852060","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Plutonium Signatures in Molten-Salt Reactor Off-Gas Tank and Safeguards Considerations 熔盐堆废气罐中的钚特征及保障措施

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-05-18 DOI: 10.3390/jne4020028

Nicholas Dunkle, Alex Wheeler, Jarod Richardson, Sandra Bogetic, Ondrej Chvala, Steven E. Skutnik

{"title":"Plutonium Signatures in Molten-Salt Reactor Off-Gas Tank and Safeguards Considerations","authors":"Nicholas Dunkle, Alex Wheeler, Jarod Richardson, Sandra Bogetic, Ondrej Chvala, Steven E. Skutnik","doi":"10.3390/jne4020028","DOIUrl":"https://doi.org/10.3390/jne4020028","url":null,"abstract":"Fluid-fueled molten-salt reactors (MSRs) are actively being developed by several companies, with plans to deploy them internationally. The current IAEA inspection tools are largely incompatible with the unique design features of liquid fuel MSRs (e.g., the complex fuel chemistry, circulating fuel inventory, bulk accountancy, and high radiation environment). For these reasons, safeguards for MSRs are seen as challenging and require the development of new techniques. This paper proposes one such technique through the observation of the reactor’s off-gas. Any reactor design using low-enriched uranium will build up plutonium as the fuel undergoes burnup. Plutonium has different fission product yields than uranium. Therefore, a shift in fission product production is expected with fuel evolution. The passive removal of certain gaseous fission products to the off-gas tank of an MSR provides a valuable opportunity for analysis without significant modifications to the design of the system. Uniquely, due to the gaseous nature of the isotopes, beta particle emissions are available for observation. The ratios of these fission product isotopes can, thus, be traced back to the relative amount and types of fissile isotopes in the core. This proposed technique represents an effective safeguards tool for bulk accountancy which, while avoiding being onerous, could be used in concert with other techniques to meet the IAEA’s timeliness goals for the detection of a diversion.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-05-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135718117","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1