THERMAL-HYDRAULICS

作品数：17被引量：23H指数：3
导出分析报告
相关领域：核科学技术更多>>
相关机构：清华大学更多>>
相关期刊：《Plasma Science and Technology》《Tsinghua Science and Technology》《Annual Report of China Institute of Atomic Energy》《Applied Mathematics》更多>>
相关基金：国家自然科学基金中国博士后科学基金更多>>
-
在结果中检索

检索结果分析

结果分析中...
选择条件：
  • 主题=NEUTRONICSx
共 条 记 录，以下是1-5
全选清除导出
参考文献引证文献引用追踪
视图：
排序：
Preliminary safety analysis for heavy water-moderated molten salt reactor
《Nuclear Science and Techniques》2024年第6期202-217,共16页Gao-Ang Wen Jian-Hui Wu Chun-Yan Zou Xiang-Zhou Cai Jin-Gen Chen Man Bao 
the National Natural Science Foundation of China(No.11905285);the Shanghai Natural Science Foundation(No.20ZR1468700);the Youth Innovation Promotion Association CAS(No.2022258).
The heavy water-moderated molten salt reactor(HWMSR)is a newly proposed reactor concept,in which heavy water is adopted as the moderator and molten salt dissolved with fissile and fertile elements is used as the fuel....
关键词：Heavy water-moderated molten salt reactor Neutronics and thermal-hydraulics coupling Transient analysis Accident analysis 
Implementation of high-fidelity neutronics and thermal–hydraulic coupling calculations in HNET被引量：3
《Nuclear Science and Techniques》2022年第11期120-132,共13页Yan-Ling Zhu Xing-Wu Chen Chen Hao Yi-Zhen Wang Yun-Lin Xu 
supported by the China Postdoctoral Science Foundation(No.2021M703045);the National Natural Science Foundation of China(No.12075067);the National Key R&D Program of China(No.2018YFE0180900).
To perform nuclear reactor simulations in a more realistic manner,the coupling scheme between neutronics and thermal-hydraulics was implemented in the HNET program for both steady-state and transient conditions.For si...
关键词：Coupling calculation High-fidelity neutronics THERMAL-HYDRAULICS Matrix-free Newton/Krylov method Transient simulation 
Flow field effect of delayed neutron precursors in liquid-fueled molten salt reactors被引量：3
《Nuclear Science and Techniques》2022年第8期16-32,共17页Xian-Di Zuo Mao-Song Cheng Yu-Qing Dai Kai-Cheng Yu Zhi-Min Dai 
supported by Strategic Pilot Science and Technology Project of Chinese Academy of Sciences (No. XD02001005)
In molten salt reactors(MSRs),the liquid fuel salt circulates through the primary loop and a part of the delayed neutron precursors(DNPs)decays outside the reactor core.To model and analyze the flow field effect of DN...
关键词：Molten salt reactor Delayed neutron precursor Nodal expansion method Coupled neutronics and thermal-hydraulics 
Core designing of a new type of TVS-2M FAs:neutronics and thermal-hydraulics design basis limits
《Frontiers in Energy》2021年第1期256-278,共23页Saeed GHAEMI Farshad FAGHIHI 
Sincere thanks are due to the Shiraz University Research Council for his financial support.
One of the most important aims of this study is to improve the core of the current VVER reactors to achieve more burn-up(or more cycle length)and more intrinsic safety.It is an independent study on the Russian new pro...
关键词：TVS-2M FAs core design basis limits VVER-1000 analysis mixture of uranium-gadolinium oxides fuels THERMAL-HYDRAULICS PARCS WIMS-D5 
Feasibility of an innovative long-life molten chloride-cooled reactor被引量：2
《Nuclear Science and Techniques》2020年第4期1-15,共15页Ming Lin Mao-Song Cheng Zhi-Min Dai 
This work was supported by Strategic Pilot Science and Technology Project of Chinese Academy of Sciences(No.XD20191031).
Molten salt-cooled reactor is one of the six GenIV reactors with promising characteristics including safety,reliability,proliferation resistance,physical protection,economics,and sustainability.In this paper,a small i...
关键词：MOLTEN salt-cooled REACTOR NEUTRONICS Radiation damage THERMAL-HYDRAULICS 
全选清除导出
共1页<1>
检索报告 对象比较 聚类工具 使用帮助 返回顶部