Search Results - "Gu, Zhixing"

Numerical study on tritium dispersion in coastal waters: The case of Hangzhou Bay, China by Nie, Baojie, Yang, Jinmin, Wang, Wei, Gu, Zhixing, Yuan, Yuan, Li, Fengchen

“…[Display omitted] •Tritium dispersion characteristics in coastal waters were investigated.•Tidal flow is a major factor in deciding tritium dispersion in…”
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Simultaneous Analysis of Hydrophobic Atractylenolides, Atractylon and Hydrophilic Sugars in Bai-Zhu Using a High-Performance Liquid Chromatography Column Tandem Technique by Gu, Zhixing, Nie, Xi, Guo, Ping, Lu, Yuehua, Chen, Bo

“…An analytical method was established using high-performance liquid chromatography coupled with diode array and evaporative light scattering detectors…”
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Review of recent gamma spectrum unfolding algorithms and their application by Li, Fei, Gu, Zhixing, Ge, Liangquan, Li, Hui, Tang, Xinyu, Lang, Xinle, Hu, Bo

“…•The first review to generally analyze widely acceptable gamma spectrum unfolding algorithms.•The first review showing latest gamma spectrum unfolding…”
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History review of nuclear reactor safety by Gu, Zhixing

“…•The history of the birth for atomic energy is reviewed.•The history of the birth for nuclear reactor safety is reviewed.•The history of the development for…”
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Experimental study of non-condensable gas effects on sonic limit of sodium heat pipe by Zhang, Muhao, Miao, Qixuan, Zhang, Suyi, Ma, Yugao, Ding, Shuhua, Zhang, Zhuohua, Gu, Zhixing

“…•Sonic limit of the 1 m-long sodium heat pipes with artery and axial groove wick are obtained.•Effects of non-condensable gas on sonic limit is experimentally…”
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U(VI) adsorption by one-step hydrothermally synthesized cetyltrimethylammonium bromide modified hydroxyapatite-bentonite composites from phosphate‑carbonate coexisted solution by Liu, Jun, Shi, Shilong, Li, Chao, Hong, Xu, Gu, Zhixing, Li, Fei, Zhai, Juan, Zhang, Qingxian, Liao, Jiali, Liu, Ning, Liu, Chunhai

“…Cetyltrimethylammonium bromide modified hydroxyapatite-bentonite composites (CTAB-HAp-Bent) were first synthesized by one-step hydrothermal method to test its…”
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Preliminary development and verification of an OpenFOAM-based multi-physics coupling safety analysis code for Lead-based reactor by Ou, Wenlan, Gong, Zhengyu, Gu, Zhixing, Pan, Qiwen, Zhang, Ling, Dai, Jianing

“…•An OpenFOAM-based multi-physics implicit coupling code with turbulence considerations for LFR was developed.•Code-to-code verification was carried out by…”
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Bubble size distribution for bubbly-to-slug transition flow in narrow rectangular channel by Zhang, Muhao, Mi, Tao, huang, Tao, Deng, Jian, He, Qingche, Gu, Zhixing, Zhang, Luteng, Ding, Shuhua, Pan, Liangming

“…•Bubble size distribution in bubbly-to-slug transition flow for narrow rectangular flow channel is experimentally measured.•The evolving characteristics of…”
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Preliminary code development for single-phase liquid natural circulation flow simulation based on two-phase compressible model by Dai, Jianing, Gu, Zhixing, Zhang, Ling, Gong, Zhengyu, Pan, Qiwen, Ou, Wenlan

“…It is of great significance to study the thermal-hydraulic characteristics of Lead-based Fast Reactor. In these years, the computational fluid dynamics method…”
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Code development of Single-phase 2-D pressure wave propagation by Gu, Zhixing, Yu, Hongxing, Dai, Jianing, Huang, Daishun, Yan, Mingyu, Shen, Yaou, Guo, Chao

“…•A 2-D single-phase pressure wave propagation calculating code is developed.•Code verifications are carried out by using two typical single-phase shock tube…”
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New semi-analytical algorithm for solving PKEs based on Euler-Maclaurin approximation by Xiao, Yunlong, Gu, Zhixing, Zhang, Qingxian, Ge, Liangquan, Zeng, Guoqiang, Li, Fei

“…Point kinetics equations (PKEs) is an significant model used to describe dynamic behaviors of neutron in nuclear reactors. How to cope with its stiffness…”
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Application of artificial neural networks to X‐ray fluorescence spectrum analysis by Li, Fei, Gu, Zhixing, Ge, Liangquan, Sun, Di, Deng, Xutao, Wang, Shun, Hu, Bo, Xu, Jingru

“…X‐ray fluorescence (XRF) is widely applied as a mature nondestructive testing method, and appropriate improvement of quantitative analysis methods can improve…”
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Verification of a HC-PK-CFD coupled program based a benchmark on beam trip transients for XADS reactor by Gu, Zhixing, Li, Fei, Ge, Liangquan, Zeng, Guoqiang, Zhang, Qingxian, Shi, Jialei

“…•A transient analysis program HC-PK-CFD is developed.•Verification of HC-PK-CFD is performed based on a benchmark on the beam trip transients for XADS…”
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Preliminary investigation on the primary heat exchanger lower head rupture accident of forced circulation LBE-cooled fast reactor by Gu, Zhixing, Wang, Gang, Bai, Yunqing, Song, Yong, Zhao, Zhumin

“…•A forced circulation LBE-cooled fast reactor was developed in China.•The steady state of this reactor was simulated by using NTC program.•The HXLHR accident…”
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Transient analyses on loss of heat sink and overpower transient of natural circulation LBE-cooled fast reactor by Gu, Zhixing, Wang, Gang, Wang, Zhen, Jin, Ming, Wu, Yican

“…Two transient analyses on a natural circulation LBE-cooled fast reactor were performed by using a Neutronics and Thermal-hydraulics Coupled Simulation Program…”
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Benchmark of Neutronics and Thermal-hydraulics Coupled Simulation program NTC on beam interruptions in XADS by Wang, Zhen, Wang, Gang, Gu, Zhixing, Jin, Ming, Wu, Yican

“…•A Neutronics and Thermal-hydraulics Coupled code is developed for transient analysis.•The spatial kinetics model was employed in the benchmark.•The simulation…”
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Comparison of transient analysis of LBE-cooled fast reactor and ADS under loss of heat sink accident by Wang, Gang, Gu, Zhixing, Wang, Zhen, Jin, Ming

“…•A natural circulation LBE-cooled research reactor is developed by Institute of Nuclear Energy Safety Technology.•The safety advantages for 10MWth fast and ADS…”
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Safety analyses of 10MWth Forced Circulation LBE-cooled Fast Reactor during unprotected transients by Gu, Zhixing, Wang, Gang, Wang, Zhen, Song, Yong, Zhao, Zhumin

“…•A Forced Circulation LBE-cooled Fast Research Reactor was developed in China.•A new Neutronics and Thermal-hydraulics Coupled safety analysis code NTC was…”
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Safety analyses of 10 MW th Forced Circulation LBE-cooled Fast Reactor during unprotected transients by Gu, Zhixing, Wang, Gang, Wang, Zhen, Song, Yong, Zhao, Zhumin

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Verification of Neutronics and Thermal-hydraulics Coupled Simulation Program NTC by the PDS-XADS transient simulation by Wang, Gang, Gu, Zhixing, Wang, Zhen, Jin, Ming

“…In this paper, the steady state and three typical transient accidents of LBE-cooled sub-critical experimental accelerator driven system reactor were simulated…”
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