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Featured researches published by Zijiang Yang.


2013 21st International Conference on Nuclear Engineering | 2013

LBLOCA Analysis of CPR1000 NPP With Advanced Accumulator

Hongwei Hu; Jianqiang Shan; Junli Gou; Bo Zhang; Haitao Wang; Zijiang Yang

Large break LOCA (LBLOCA) is one of the limit design basic accidents in nuclear power plant. The large flow water in the advanced accumulator is injected into primary loop in early short time. When the vessel pressure drops and reactor core is re-flooded, the advanced accumulator provides a small injection flow to keep the reactor core in flooded condition. Thus, the startup grace time of the low pressure safety injection pump is extended, and the core still stays in a long-term cooling state. By deducing the original accumulator model in RELAP5 accident analysis code, a new model combining the advanced and the traditional accumulator is obtained and coupled into RELAP5/ MOD 3.3. Simulation results show that there is a large flow in the advanced accumulator at the initial stage. When the accumulator water level is lower than the stand pipe, a vortex appears in the damper, resulting in a large pressure drop and small flow. The phenomenon meets the demand of the advanced accumulator design and the simulation of the advanced accumulator is accomplished successfully. Based on this, the primary coolant loop cold leg double-ended guillotine break LBLOCA in CPR1000 is analyzed with the modified RELAP5 code. When the double ended cold leg guillotine accident with 200s delayed startup of the low pressure safety injection occurs, maximum cladding temperature in the core with traditional accumulator is 1860K which seriously exceeded the safety temperature (1477K)[1] prescribed limits while the maximum cladding temperature with advanced accumulator has the security temperature-1277K. From this point of view, adopting passive advanced accumulator can strive a longer grace time for LPSI. Thus the reliability, security and economy of reactor system were improved.Copyright


Annals of Nuclear Energy | 2017

An assessment of heat transfer models of water flow in helically coiled tubes based on selected experimental datasets

Junli Gou; Haifu Ma; Zijiang Yang; Jianqiang Shan


Nuclear Engineering and Design | 2017

Preliminary assessment of a combined passive safety system for typical 3-loop PWR CPR1000

Zijiang Yang; Jianqiang Shan; Junli Gou


Progress in Nuclear Energy | 2016

Study on startup characteristics of heat pipe cooled and AMTEC conversion space reactor system

Yuan Yuan; Jianqiang Shan; Bin Zhang; Junli Gou; Bo Zhang; Tianyu Lu; Li Ge; Zijiang Yang


International Journal of Heat and Mass Transfer | 2018

Experimental study of vertical and horizontal two-phase pipe flow through double 90 degree elbows

Zhuoran Dang; Zijiang Yang; Xiaohong Yang; Mamoru Ishii


Nuclear Science and Techniques | 2017

Analysis of SBLOCA on CPR1000 with a passive system

Zijiang Yang; Junli Gou; Jianqiang Shan; Pan Wu


Annals of Nuclear Energy | 2017

Analysis of loss of residual heat removal system for CPR1000 under cold shutdown operation

Junli Gou; Haifu Ma; Zijiang Yang; Jianqiang Shan


Nuclear Engineering and Design | 2018

SGTR analysis on CPR1000 with a passive safety system

Zijiang Yang; Jianqiang Shan; Junli Gou; Mamoru Ishii


International Journal of Multiphase Flow | 2018

Experimental study on void fraction, pressure drop and flow regime analysis in a large ID piping system

Zhuoran Dang; Zijiang Yang; Xiaohong Yang; Mamoru Ishii


International Journal of Heat and Mass Transfer | 2018

Downward two phase flow experiment and general flow regime transition criteria for various pipe sizes

Zijiang Yang; Zhuoran Dang; Xiaohong Yang; Mamoru Ishii; Jianqiang Shan

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Jianqiang Shan

Xi'an Jiaotong University

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Junli Gou

Xi'an Jiaotong University

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Bin Zhang

Xi'an Jiaotong University

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Bo Zhang

Xi'an Jiaotong University

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Li Ge

Xi'an Jiaotong University

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Tianyu Lu

Xi'an Jiaotong University

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Yuan Yuan

Xi'an Jiaotong University

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