Zobrazeno 1 - 10
of 22
pro vyhledávání: '"Longze Li"'
Publikováno v:
Scientific Reports, Vol 14, Iss 1, Pp 1-15 (2024)
Abstract With the increased use of data-driven approaches and machine learning-based methods in material science, the importance of reliable uncertainty quantification (UQ) of the predicted variables for informed decision-making cannot be overstated.
Externí odkaz:
https://doaj.org/article/8afafdddc7b945d58ed0f1759471b450
Publikováno v:
Journal of Materials Engineering & Performance; Oct2023, Vol. 32 Issue 19, p8585-8592, 8p
Publikováno v:
Kerntechnik. 86:224-228
In order to reduce the work burden during the training and drilling of the severe accident and severe accident management guidelines, and improve the implementation efficiency of the guidelines, a method of digitizing the SAMG program files is propos
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7581cc07e21883cc61e38d4151b7c3f0
https://doi.org/10.1515/kern-2019-0114
https://doi.org/10.1515/kern-2019-0114
Autor:
Shiwei Yao, Yun Tai, Longze Li, Jue Wang, Xiaofan Hou, Jinrong Qiu, Wen Yang, Fei Chao, Chuan He
Publikováno v:
Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation.
The Floating nuclear power plant (FNPP) is a kind of marine nuclear power plant which takes barge as carrier and is fixed in specific sea area by mooring device. A 100 MWt PWR type small modular reactor (SMR) with 2 loops is used in the FNPP. It is d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6feaa8c3f5e04185c4a9bac83be372e8
https://doi.org/10.1115/icone28-64611
https://doi.org/10.1115/icone28-64611
Publikováno v:
Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications.
The neutron and photon flux rates are important parameters for safe reactor operation, refueling and decommissioning, scientific applications and radiation protection. For the Integrated small pressurized water reactor, the advanced reactor core anal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f7f000fa327f1d635a46a0314425b032
https://doi.org/10.1115/icone28-64448
https://doi.org/10.1115/icone28-64448
Publikováno v:
Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics.
Natural circulation refers to the phenomenon of fluid circulation driven by the driving force formed by the density difference and height difference. Natural circulation is very common in nuclear power system, which has an important impact on reactor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::43581ef63987fb46b06e0f5e44ad2c0b
https://doi.org/10.1115/icone28-64367
https://doi.org/10.1115/icone28-64367
Publikováno v:
Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics.
It is well know that the two-fluid single pressure model is currently widely used to analyze reactor transient accidents such as LOCA. Current mainstream reactor safety analysis codes such as RALAP5 and CATHARE are based on this single pressure model
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::53ed0b7df2bb8a1ae73e2df059d11a98
https://doi.org/10.1115/icone28-64434
https://doi.org/10.1115/icone28-64434
Autor:
Wenxi Tian, Ping Song, Jun Wang, Tangtao Feng, Longze Li, Mingjun Wang, Guanghui Su, Suizheng Qiu
Publikováno v:
Progress in Nuclear Energy. 111:174-182
A new simple core degradation experiment will be conducted to investigate the distribution of mass and energy during a core degradation process, and the International Standard Problem (ISP) No.31 is chosen as a pre-simulation for the new experiment.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4fcfe2659265b5e0589040c96471614d
https://doi.org/10.1016/j.pnucene.2018.11.004
https://doi.org/10.1016/j.pnucene.2018.11.004
Autor:
Wenxi Tian, Suizheng Qiu, Longze Li, Tae Woon Kim, Guanghui Su, Shripad T. Revankar, Yapei Zhang
Publikováno v:
Progress in Nuclear Energy. 100:197-208
A natural circulation small modular reactor (NCSMR) is designed and the severe accident of the NCSMR was analyzed with MELCOR code in this work. The NCSMR is a 330 MWt light water reactor no reactor coolant pumps and no active safety injection system
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::daa52945b303f4c85b2284e5ca16ee37
https://doi.org/10.1016/j.pnucene.2017.06.003
https://doi.org/10.1016/j.pnucene.2017.06.003
Publikováno v:
Progress in Nuclear Energy. 124:103248
The application of passive safety systems (PSSs) can greatly improve the safety level of the Offshore Floating Nuclear Power Plants. As one of the important component of PSSs, the secondary passive residual heat removal system can be seen as the mult
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2521d4f591950b1352659b29d3471263
https://doi.org/10.1016/j.pnucene.2020.103248
https://doi.org/10.1016/j.pnucene.2020.103248