云南高校图书馆联盟文献共享服务平台- THERMAL-HYDRAULICS

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>>

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

A comprehensive CFD combustion model for supercritical CFB boilers被引量：8: 《Particuology》2019年第2期29-37,共9页Linjie Xu Leming Cheng JieqiangJi Qinhui Wang Mengxiang Fang; A combustion model of a large-scale supercritical circulati ng fluidized bed (CFB) boiler was developed for comprehensive computational-fluid-dynamics analysis. The model incorporates gas-solid hydrodynamics, coal com...; 关键词：COMPREHENSIVE combustion model Computational fluid dynamic THERMAL-HYDRAULICS SUPERCRITICAL CIRCULATING fluidized BED Large-scale FURNACE

Development of a dynamics model for graphite-moderated channel-type molten salt reactor被引量：3: 《Nuclear Science and Techniques》2019年第1期145-155,共11页Long He Cheng-Gang Yu Rui-Min Ji Wei Guo Ye Dai Xiang-Zhou Cai; supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000);the Frontier Science Key Program of the Chinese Academy of Sciences(No.QYZDY-SSW-JSC016);the National Natural Science Foundation of China Key Program(No.91326201); A molten salt reactor(MSR) is one of the six advanced reactor concepts selected by the generation Ⅳ international forum because of its advantages of inherent safety, and the promising capabilities of Th-U breeding an...; 关键词：MOLTEN SALT REACTOR THERMAL-HYDRAULICS Point REACTOR model Thermal coupling

Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics and structural analyses: 《Frontiers of Mechanical Engineering》2018年第4期563-570,共8页Jinya KATSUYAMA Shumpei UNO Tadashi WATANABE Yinsheng LI; The thermal hydraulic （TH） behavior of coo- lant water is a key factor in the structural integrity assessments on reactor pressure vessels （RPVs） of pressurized water reactors （PWRs） under pressurized thermal sh...; 关键词：structural integrity reactor pressure vessel pressurized thermal shock thermal hydraulic analysis pressurized water reactor weld residual stress

Analytical and Computational Analysis of Flow Splitting in Multiple, Parallel Channels Systems: 《World Journal of Nuclear Science and Technology》2016年第3期170-190,共22页Alejandro I. Lazarte J. C. Ferreri; Previous analytical results on flow splitting are generalized to consider multiple boiling channels systems. The analysis is consistent with the approximations usually adopted in the use of systems codes (like RELAP5 ...; 关键词：Multiple Parallel Boiling Channels Systems Asymmetric Splitting Flow Verification of Codes Systems Thermal-Hydraulics Codes Nuclear Engineering

The General Design and Technology Innovations of CAP1400被引量：3: 《Engineering》2016年第1期103-111,共9页郑明光严锦泉申屠军田林王煦嘉邱忠明; A historical review of in-vessel melt retention （IVR） is given, which is a severe accident mitigation mea- sure extensively applied in Generation III pressurized water reactors （PWRs）. The idea of IVR actually ori...; 关键词：Pressurized water reactor Severe accident In-vessel melt retention Debris formationDebris remeltingMelt pool formationMelt pool thermal-hydraulicsCritical heat flux

THERMAL-HYDRAULICS