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Analytical solution of modified point kinetics equations for linear reactivity variation in subcritical nuclear reactors adopting an incomplete gamma function approximation
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作者 André Luiz Pereira Rebello Junior Aquilino Senra Martinez Alessandro da Cruz Goncalves 《Natural Science》 2012年第11期919-923,共5页
The present work aims to achieve a fast and accurate analytical solution of the point kinetics equations applied to subcritical reactors such as ADS (Accelerator-Driven System), assuming a linear reactivity and extern... The present work aims to achieve a fast and accurate analytical solution of the point kinetics equations applied to subcritical reactors such as ADS (Accelerator-Driven System), assuming a linear reactivity and external source variation. It was used a new set of point kinetics equations for subcritical systems based on the model proposed by Gandini & Salvatores. In this work it was employed the integrating factor method. The analytical solution for the case of interest was obtained by using only an approximation which consists of disregarding the term of the second derivative for neutron density in relation to time when compared with the other terms of the equation. And also, it is proposed an approximation for the upper incomplete gamma function found in the solution in order to make the computational processing faster. In addition, for purposes of validation and comparison a numerical solution was obtained by the finite differences method. Finally, it can be concluded that the obtained solution is accurate and has fast numerical processing time, especially when compared with the results of numerical solution by finite difference. One can also observe that the gamma approximation used achieve a high accuracy for the usual parameters. Thus we got satisfactory results when the solution is applied to practical situations, such as a reactor startup. 展开更多
关键词 accelerator-driven System subcritical reactors POINT Kinetics Equations INCOMPLETE Gamma Functions
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Design and R&D Progress of China Lead-Based Reactor for ADS Research Facility 被引量:29
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作者 Yican Wu 《Engineering》 SCIE EI 2016年第1期124-131,共8页
In 2011,the Chinese Academy of Sciences launched an engineering project to develop an acceleratordriven subcritical system(ADS)for nuclear waste transmutation.The China Lead-based Reactor(CLEAR),proposed by the Instit... In 2011,the Chinese Academy of Sciences launched an engineering project to develop an acceleratordriven subcritical system(ADS)for nuclear waste transmutation.The China Lead-based Reactor(CLEAR),proposed by the Institute of Nuclear Energy Safety Technology,was selected as the reference reactor for ADS development,as well as for the technology development of the Generation IV lead-cooled fast reactor.The conceptual design of CLEAR-I with 10 MW thermal power has been completed.KYLIN series lead-bismuth eutectic experimental loops have been constructed to investigate the technologies of the coolant,key components,structural materials,fuel assembly,operation,and control.In order to validate and test the key components and integrated operating technology of the lead-based reactor,the lead alloy-cooled non-nuclear reactor CLEAR-S,the lead-based zero-power nuclear reactor CLEAR-0,and the lead-based virtual reactor CLEAR-V are under realization. 展开更多
关键词 accelerator-driven subcritical system (ADS) China Lead-based reactor (CLEAR) Lead-bismuth eutectic (LBE)Technology R&D
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Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT 被引量:1
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作者 Ranjana Nath-M 《World Journal of Nuclear Science and Technology》 2021年第1期43-64,共22页
Radiopharmaceuticals are used in nuclear medicine for diagnostic or therapeutic acts. The short decay half-lives of medical radioisotopes, especially those used for diagnostics, imply that they should be produced cont... Radiopharmaceuticals are used in nuclear medicine for diagnostic or therapeutic acts. The short decay half-lives of medical radioisotopes, especially those used for diagnostics, imply that they should be produced continuously and transported as quickly as possible to the medical units where they are used. Neutron-rich medical radioisotopes are generally produced in research reactors, like technetium-99m, lutetium-177, holmium-166 and iodine-131. On the other hand, proton-rich radioisotopes are produced via reactions with charged particles from accelerators like fluorine-18, gallium-67, iodine-123 and thallium-201. Beside this, innovative nuclear reactors are advocated as solutions to the issues of nuclear waste production and proliferation threats. Fast neutron, thorium-cycle and accelerator-driven subcritical (ADS) reactors are some of the most promising of them, proposed as safer fuel breeders and “waste burners”. This article examines the use of a fast thorium-cycle ADS with liquid lead-bismuth eutectic coolant for the production of molybdenum-99/technetium-99m and lutetium-177. Burnup simulation has been made with the Monte-Carlo (MC) code SERPENT. It is demonstrated that MC codes can advantageously be used to determine the optimal irradiation time for a given radioisotope in a realistic reactor core. It is also shown that fast thorium-cycle ADS is an economical option for the production of medical radioisotopes. 展开更多
关键词 Medical Radioisotopes Molybdenum-99 Technetium-99m Lutetium-177 fast reactor Thorium Cycle subcritical reactor ADS Spallation Activation Burnup SERPENT
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ADS加速器失束次临界反应堆动态特性研究 被引量:1
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作者 于涛 李吉根 +3 位作者 凌球 史永谦 罗璋琳 戎永华 《核科学与工程》 CSCD 北大核心 2007年第3期230-233,共4页
加速器驱动系统(ADS)中次临界堆芯的功率水平依靠强流质子轰击散裂靶产生的中子源来维持。加速器较为频繁的失束问题,必将对ADS次临界反应堆安全性产生影响。研究了ADS系统失束事故特性,设计开发出具有较强针对性的用于ADS失束事故分析... 加速器驱动系统(ADS)中次临界堆芯的功率水平依靠强流质子轰击散裂靶产生的中子源来维持。加速器较为频繁的失束问题,必将对ADS次临界反应堆安全性产生影响。研究了ADS系统失束事故特性,设计开发出具有较强针对性的用于ADS失束事故分析软件,对加速器驱动快中子次临界反应堆的动态响应开展了初步研究。结论表明仅靠断束停堆,仍有可能危及次临界反应堆的安全性。建议增设辅助停堆保护系统以提高ADS安全性。 展开更多
关键词 ADS 失束 次临界 快堆 安全
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加速器驱动次临界快堆初装堆芯的功率密度分布展平 被引量:2
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作者 李浩泉 杨永伟 经荥清 《清华大学学报(自然科学版)》 EI CAS CSCD 北大核心 2004年第6期751-753,757,共4页
为了降低以 (U、Pu、Np、Am、Cm) O2 为燃料的加速器驱动次临界快堆 (ADSFR)堆芯径的功率峰因子 ,将堆芯精细地分为燃料高、低富集度区。采用耦合散裂中子源的产生 (L AHET)、中子输运 (MCNP)和核素燃耗 (ORI-GEN2 )等计算程序的 COU P... 为了降低以 (U、Pu、Np、Am、Cm) O2 为燃料的加速器驱动次临界快堆 (ADSFR)堆芯径的功率峰因子 ,将堆芯精细地分为燃料高、低富集度区。采用耦合散裂中子源的产生 (L AHET)、中子输运 (MCNP)和核素燃耗 (ORI-GEN2 )等计算程序的 COU PL E程序系统进行计算分析。结果显示 ,在设定的 0 .97初始临界度下 ,富集度分割比为 1.5时将给出最有利的结果 :初始的全堆功率峰因子为 1.6 92 ;以 84 0 MW的热功率运行过程中 ,尽管全堆的功率峰因子不断升高 ,但至 30 0 d时 ,只达到 1.96 3。 展开更多
关键词 反应堆物理 加速器驱动次临界快堆 功率展平 功率峰因子
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Microstructure and Mechanical Properties of Simulated Heat-affected Zones of EP-823 Steel for ADS/LFR 被引量:1
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作者 Shanping Lu Tian Liang +3 位作者 Yongkui Li Dianzhong Li Lijian Rong Yiyi Li 《Journal of Materials Science & Technology》 SCIE EI CAS CSCD 2015年第8期864-871,共8页
EP-823 steel is one of the candidate materials for accelerator-driven systems/lead-cooled fast reactors (ADS/LFR). Its weldability was investigated by mechanical property tests and microstructure analysis on the enl... EP-823 steel is one of the candidate materials for accelerator-driven systems/lead-cooled fast reactors (ADS/LFR). Its weldability was investigated by mechanical property tests and microstructure analysis on the enlarged heat-affected zones (HAZs) made by numerical and physical simulation. The finite element numerical simulation could simulate the welding thermal cycle of the characteristic regions in HAZs with extremely high accuracy, The physical simulation performed on a Gleeble simulator could enlarge the characteristic regions to easily investigate the relationship between the microstructure evolution and the mechanical properties of the HAZs. The results showed that the simulated partially normalized zone comprising tempered martensite, newly formed martensite and more tiny carbides has the highest impact energy. The fully normalized zone exhibits the highest hardness because of the quenched martensite and large carbides. The ductile property of the overheated zone is poor for the residual delta- ferrite phases and the quenched martensite. 展开更多
关键词 accelerator-driven systems/lead-cooled fast reactors (ADS/LFR) EP-823 steel Heat-affected zones (HAZs) Microstructure evolution Mechanical property
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