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Probabilistic monitoring of nuclear plants using R-vine copula 期刊论文
Annals of Nuclear Energy, 2023
作者:  Amin, Md Tanjin;  Yao, Yuantao;  Yu, Jie;  Adumene, Sidum
收藏  |  浏览/下载：21/0  |  提交时间：2023/11/16
A new approach for fault diagnosis with full-scope simulator based on state information imaging in nuclear power plant 期刊论文
Annals of Nuclear Energy, 2020
作者:  Yao, Yuantao;  Wang, Jin;  Xie, Min;  Hu, Liqin;  Wang, Jianye
收藏  |  浏览/下载：14/0  |  提交时间：2023/11/15
Heat transfer characteristic analysis of a novel annular nuclear heat exchanger for propulsion system 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 126, 期号: 无, 页码: 84-94
作者:  Bai, Ying;  Zhao, Zhumin;  Xu, Gang;  Bai, Yunqing
浏览  |  Adobe PDF(3188Kb)  |  收藏  |  浏览/下载：100/24  |  提交时间：2020/05/21
Annular channel  Nuclear thermal propulsion  Enhanced convection heat transfer  Performance optimization  
Stability analysis on flow parameters in coolant temperature control system of lead-cooled fast reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 126, 期号: 无, 页码: 367-375
作者:  Yao, Yuantao;  Wang, Jianye;  Zhang, Junjun;  Yang, Minghan
浏览  |  Adobe PDF(1997Kb)  |  收藏  |  浏览/下载：132/52  |  提交时间：2020/05/21
Lead-cooled fast reactor  Coolant temperature control system  Coolant flow rate  Stability analysis  Real stability radius  
Research on the application of burnable poison ZrB2 and Gd2O3 in a small modular lead-based thermal reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 124, 期号: 无, 页码: 21-27
作者:  Sun, Yanting;  Yang, Qi;  Gao, Jun;  Liu, Chao;  Jin, Ming
浏览  |  Adobe PDF(1768Kb)  |  收藏  |  浏览/下载：111/44  |  提交时间：2019/12/25
Burnable poison  Reactivity  Burnup  ZrB2  Gd2O3  
Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 122, 期号: 无, 页码: 155-162
作者:  Jamil, Zeeshan;  Zou, Jun;  Hao, Lijuan;  Hu, Liqin
浏览  |  Adobe PDF(2494Kb)  |  收藏  |  浏览/下载：86/38  |  提交时间：2019/12/25
Validation/Benchmarking  HENDL  BFS-62-3A  SuperMC  Heterogeneous  Criticality  Reactivity effects  Spectral indices  Fission rates  Sensitivity study  
Flow and heat transfer behaviors for double-walled-straight-tube heat exchanger of HLM loop 期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 120, 期号: 无, 页码: 604-610
作者:  Liu, Shuyong;  Jin, Ming;  Lyu, Kefeng;  Zhou, Tao;  Zhao, Zhumin
浏览  |  Adobe PDF(1934Kb)  |  收藏  |  浏览/下载：84/31  |  提交时间：2019/11/11
HLM  KYLIN-II  Double wall tube  Powder gap  Non-uniform flow  Thermal resistance  
Numerical investigation of the core outlet temperature fluctuation for the lead-based reactor 期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 117, 期号: 无, 页码: 194-201
作者:  Wang, Lizhi;  Wu, Guowei;  Wang, Jin;  Jin, Ming;  Song, Yong
浏览  |  Adobe PDF(3527Kb)  |  收藏  |  浏览/下载：76/35  |  提交时间：2019/08/23
Temperature fluctuation  Lead-based reactor  Core outlet  
Validation of SuperMC with BEAVRS benchmark at hot zero power condition 期刊论文
ANNALS OF NUCLEAR ENERGY, 2018, 卷号: 111, 期号: 无, 页码: 709-714
作者:  Wang, Zhiyan;  Wu, Bin;  Hao, Lijuan;  Liu, Hongfei;  Song, Jing
浏览  |  Adobe PDF(3818Kb)  |  收藏  |  浏览/下载：92/42  |  提交时间：2019/06/17
SuperMC  BEAVRS  Monte Carlo  Validation  
Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient 期刊论文
ANNALS OF NUCLEAR ENERGY, 2017, 卷号: 103, 期号: 无, 页码: 1-9
作者:  Wu, Guowei;  Jin, Ming;  Li, Yazhou
浏览  |  Adobe PDF(4145Kb)  |  收藏  |  浏览/下载：124/88  |  提交时间：2018/05/17
Coast-down  Flow Halving Time (Fht)  Lead Cooled Fast Reactor (Lfr)  Loss Of Flow (lOf)