THERMAL-HYDRAULICS

作品数：17被引量：23H指数：3
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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 
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 
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 
Scaling Analysis of Thermal-Hydraulics for Steam Generator Passive Heat Removal System
《Journal of Shanghai Jiaotong university(Science)》2014年第2期219-225,共7页周源 林萌 陈金波 王汉林 
the National Science and TechnologyMajor Project of China(No.2011ZX06004-008)
Steam generator passive heat removal system(SG-PHRS) is used as a passively safe mode to provide decay heat removal in some advanced pressurized water reactors. Due to the structure characteristics of steam generator(...
关键词：steam generator natural circulation scaling simulation thermal hydraulics 
Numerical Simulations of Upper Plenum Thermal-Hydraulics of Monju Reactor Vessel Using High Resolution Mesh Models
《Journal of Energy and Power Engineering》2013年第4期679-688,共10页Hiroaki Ohira Kei Honda Masutake Sotsu 
In order to evaluate the effects of the FHs （flow holes） on the inner barrel, which were installed in the upper plenum of the Monju reactor vessel, a high resolution meshes around the FHs was constructed. Using this...
关键词：Monju reactor vessel upper plenum THERMAL-HYDRAULICS numerical simulation flow holes. 
Consideration for Thermal-Hydraulics Limiting Design Parameters of SFR Plant
《Annual Report of China Institute of Atomic Energy》2007年第1期7-8,共2页LIU Yi-zhe, YU Hong 
With a series of principles, the thermal-hydraulics design criteria of SFR plant has been considered and described in this paper.The primary objective of thermal-hydraulics design is to ensure that adequate flow of co...
关键词：核物理 核能 反应堆 水热限制设计参数 
Thermal-hydraulic Stability Analysis of Nuclear Heating Reactors
《Tsinghua Science and Technology》1996年第1期23-26,共4页李金才 高祖瑛 张作义 
The two-phase flow instability that can occur in a natural circulation system is of importance in the design of nuclear heating reactors. The time domain code RETRAN-02 and the frequency domain code NUFREQ were applie...
关键词：nuclear heating reactor (NHR) THERMAL-HYDRAULICS SAFETY flow instability 
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