Journal of Nuclear Engineering and Radiation Science最新文献_第3页

Editorial Message to Journal Readers 给期刊读者的社论信息

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-10-14 DOI: 10.1115/1.4063758

Igor Pioro

引用次数: 0

Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor 碳化硼用于LOTUS小快堆反应性长期控制的可行性研究

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-10-13 DOI: 10.1115/1.4063739

Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran

{"title":"Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor","authors":"Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran","doi":"10.1115/1.4063739","DOIUrl":"https://doi.org/10.1115/1.4063739","url":null,"abstract":"Abstract LOTUS reactor core is a small modular lead-cooled fast reactor with designed power of 200 MWth under development at VNU University of Science, Hanoi for a floating nuclear power plant application. For that purpose, advanced passive safety features and no refuelling requirement are the priorities in the core design process. To endure the continuous operation over a long lifetime, the start-up core exhibits excess reactivity to cover the reactivity loss due to burnup. The reactivity control system includes burnable poison and absorber rods and layers made of B4C which are employed in the reactor to minimize the excess reactivity of the core to about 1 $ to enhance the safety features of the core. The burnable poison is fixed inside the reactor while absorber rods/absorber layers were withdrawn or inserted in sequence to achieve the required excess reactivity of about 700 pcm. The reactivity control was arranged into ten steps to achieve the operating time of 15 effective full-power years without refuelling. Good neutronics behaviour of the core was observed with negative fuel temperature coefficient and coolant void reactivity and maximum radial power peaking factor of 1.32. However, a quite large residual absorption caused by fixed burnable poison inside fuel assemblies was revealed. In further study, to increase the neutron absorption efficiency of burnable poison in the fast spectrum as well as the reactor lifetime, a neutron moderator will be considered to add into the burnable poison rods.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"46 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135918087","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

Cold Crucible Facility for Severe Accident Research at CNL 中国科学院重大事故研究用冷坩埚装置

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-10-07 DOI: 10.1115/1.4063673

Robert David, Blake Mitchell, Justin Spencer, Norm Lair, Sergei Petoukhov

引用次数: 0

A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations 熔盐堆中子计算的一维一致多群扩散模型

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-10-06 DOI: 10.3390/jne4040041

Mohamed Elhareef, Zeyun Wu, Massimiliano Fratoni

{"title":"A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations","authors":"Mohamed Elhareef, Zeyun Wu, Massimiliano Fratoni","doi":"10.3390/jne4040041","DOIUrl":"https://doi.org/10.3390/jne4040041","url":null,"abstract":"Molten Salt Reactors (MSRs) have recently gained resurged research and development interest in the advanced reactor community. Several computational tools are being developed to capture the strong neutronics/thermal-hydraulics coupling effect in this special reactor configuration. This paper presents a consistent one-dimensional (1D) multigroup neutron diffusion model for MSR analysis, with the primary aim for fast and accurate calculations for long transients, as well as sensitivity and uncertainty analysis of the reactor. A fictitious radial leakage cross section is introduced in the model to properly account for the radial leakage effects of the reactor. The leakage cross section and other consistent neutronics parameters are generated with the Monte Carlo code Serpent using high-fidelity three-dimensional (3D) models. The accuracy of the 1D consistent model is verified by the reference solution from the Monte Carlo model on the Molten Salt Reactor Experiment (MSRE) configuration. The 1D consistent model successfully reproduced the integrated flux from the 3D model and the reactor multiplication factor keff with the error in the range of 95 to 397 pcm (per cent mille), depending on discretized energy group structures. The developed model is also extended to estimate the reactivity loss due to fuel circulation in MSRE. The estimate of reactivity loss in dynamics analysis is in great agreement with the experimental data. This model functions as the first step in the development of a 1D fully neutronics/thermal-hydraulics coupled model for short- and long-term MSRE transient analysis.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"5 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2023-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135351347","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

The Peculiarities of the German Uranium Project (1939–1945) 德国铀计划的特殊性(1939-1945)

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-09-13 DOI: 10.3390/jne4030040

Manfred Popp, Piet de Klerk

引用次数: 0

Feasibility Study on Production of High-Purity Rhenium-185 by Nuclear Transmutation of Natural Tantalum 天然钽核嬗变生产高纯铼-185的可行性研究

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-09-01 DOI: 10.3390/jne4030039

Yuki Tanoue, Tsugio Yokoyama, Masaki Ozawa

引用次数: 0

On Frequency / Time Invariance of Certain Temporal and Complex Transfer Functions for the 1d Interfacial Monochromatic Neutron Density Wave 一维界面单色中子密度波某些时间和复传递函数的频时不变性

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-08-30 DOI: 10.1115/1.4063291

N. Haidar

{"title":"On Frequency / Time Invariance of Certain Temporal and Complex Transfer Functions for the 1d Interfacial Monochromatic Neutron Density Wave","authors":"N. Haidar","doi":"10.1115/1.4063291","DOIUrl":"https://doi.org/10.1115/1.4063291","url":null,"abstract":"\u0000 Optimization of dynamical multibeam neutron cancer therapy has recently been shown to be possible via employment of the beam frequencies of neutron waves as a control variable. The concepts of transfer functions, addressed in this paper, can be essential ingredients of such optimization. Accordingly, we study the dynamics of a 1D monochromatic neutron density wave generated by time modulation of a boundary neutron current. It is demonstrated that a certain temporal transfer function of both parabolic (diffusion) and low frequency hyperbolic (P?1 transport) interfacial neutron density wave happens to be frequency non-invariant with a vibrating boundary neutron current. It is proved that, only at high frequencies, both parabolic and hyperbolic interfacial neutron waves turn out to have a fully frequency-invariant and time-invariant temporal transfer function relative to such a vibrating neutron beam at the boundary. The frequency response of an associated complex transfer function is studied and demonstrated to change behavior, from a lag compensator to a fixed gain amplifier, with changing the frequency, neutron absorption and employed theory for neutron diffusion. A highlight of this paper is its illustration that mere continuity of these transfer functions can be a reflection of the correctness of the transport theory employed for modeling the neutron density waves.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"26 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79158023","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

“Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)” 50mwell级压水堆-小型模块化堆(Pwr-Smr)系统热工模型的开发与测试

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-08-24 DOI: 10.1115/1.4063240

Shu Jun Wang, Xianmin Huang, Y. Rao, B. Bromley

{"title":"“Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”","authors":"Shu Jun Wang, Xianmin Huang, Y. Rao, B. Bromley","doi":"10.1115/1.4063240","DOIUrl":"https://doi.org/10.1115/1.4063240","url":null,"abstract":"\u0000 This paper describes the development, analysis, testing of a RELAP5-3D system thermal-hydraulics model for a 50-MWel-class pressurized water reactor - small modular reactor (PWR-SMR), similar to that by NuScale Power. This study focuses on a series of sensitivity tests to investigate the impacts of model changes. Parameters considered in the sensitivity study included the surge line junction resistance (SLJR), steam generator (SG) heat transfer area (SGHTA), SG primary flow area (SGPFA), SG secondary pressure (SGSP), and SG secondary flow rate (SGSF). Results for the reference and sensitivity simulations are compared with available design data. The flow in the primary circuit of the PWR-SMR is driven by natural circulation, and can be sensitive to changes in hydraulic resistance and pressure drop in system components. Initial results demonstrated significant flow oscillations. As a result of sensitivity studies, it was found that the surge line junction resistance needed to be increased to a factor of 30 to reduce mass flow oscillations to less than ±2%. Modifications to the steam generator heat transfer area, primary flow area, or secondary pressure have very little impact in reducing flow oscillations. However, it was found that the steam generator secondary flow rate will affect primary circuit flow oscillations, and when the SGSF was artificially increased from 68 kg/s (design data) to 91 kg/s (a 36% increase), the oscillations were eliminated, along with better matching with design data for core flow rate and inlet/outlet temperatures.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"14 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-08-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88457333","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

Experimental Study Of Helium Stratification In Multi-Compartment Containment Studies Facility 多室密封装置中氦分层的实验研究

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-08-24 DOI: 10.1115/1.4063239

B. Gera, P. Sharma, A. Karanam, Shubham Mishra, T. I., Nandan Saha, A. Dutta, P. Goyal, V. Verma, J. Chattopadhyay

{"title":"Experimental Study Of Helium Stratification In Multi-Compartment Containment Studies Facility","authors":"B. Gera, P. Sharma, A. Karanam, Shubham Mishra, T. I., Nandan Saha, A. Dutta, P. Goyal, V. Verma, J. Chattopadhyay","doi":"10.1115/1.4063239","DOIUrl":"https://doi.org/10.1115/1.4063239","url":null,"abstract":"\u0000 A significant amount of hydrogen may be released inside the containment of water cooled nuclear power reactor under postulated accident conditions. Its distribution in the multi-compartment containment geometry must be known to manage and mitigate the local hydrogen concentration in combustible pockets. An experimental study to characterize the behavior of a lighter gas (helium in place of hydrogen) in a multi-compartment Containment Studies Facility (CSF) has been pursued. Helium distribution experiments have been performed in CSF by varying important accident parameters like helium release rate, duration and injection area. The experimental studies performed in CSF depict helium stratification in the upper dome region. Stratification in terms of stratification/effective stratification factor determined for a range of experiments. The present experimental studies are important for understanding hydrogen distribution characteristics in multi-compartment containment geometry and benchmarking of CFD codes. Based on these studies some important prevailing practices for recombiner placement were endorsed.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":"8 1","pages":""},"PeriodicalIF":0.4,"publicationDate":"2023-08-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91273514","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

A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels 高含量低浓缩铀燃料验证数据集候选数据综述

IF 0.4

Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-08-16 DOI: 10.3390/jne4030038

M. DeHart, J. Bess, G. Ilas

引用次数: 0