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pro vyhledávání: '"Mao, Yulong"'
Fine-tuning large-scale pre-trained models is inherently a resource-intensive task. While it can enhance the capabilities of the model, it also incurs substantial computational costs, posing challenges to the practical application of downstream tasks
Externí odkaz:
http://arxiv.org/abs/2405.17357
Autor:
Huang, Kaiyu, Mo, Fengran, Li, Hongliang, Li, You, Zhang, Yuanchi, Yi, Weijian, Mao, Yulong, Liu, Jinchen, Xu, Yuzhuang, Xu, Jinan, Nie, Jian-Yun, Liu, Yang
The rapid development of Large Language Models (LLMs) demonstrates remarkable multilingual capabilities in natural language processing, attracting global attention in both academia and industry. To mitigate potential discrimination and enhance the ov
Externí odkaz:
http://arxiv.org/abs/2405.10936
Publikováno v:
In Annals of Nuclear Energy 15 June 2024 201
Akademický článek
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Autor:
Mao Yulong, Meng Shuqi, Lu Xianghui, Jin Desheng, Wang Xiaoting, Li Kejia, Hu Yisong, Hu Yousen, Rui Min
Publikováno v:
Frontiers in Energy Research, Vol 11 (2023)
During the power operation of nuclear reactors, the corrosion products in the secondary circuit will deposit on the inside of Helical-coiled One-Through Steam Generator (H-OTSG) heat transfer tubes and form fouling. The main component of fouling is i
Externí odkaz:
https://doaj.org/article/afee43b7edc643cab54b6a73797c87ef
Publikováno v:
In Annals of Nuclear Energy 1 September 2022 174
Autor:
Xue, Chaochao, Mao, Yulong, Zhang, Ziyu, Tan, Jibo, Wu, Xinqiang, Han, En-Hou, Ruan, Tianming, Li, Jinggang, Liao, Jiapeng
Publikováno v:
In Journal of Nuclear Materials September 2022 568
Autor:
Zhang, Weiwei, Bai, Xueyan, Liu, Tingting, Mao, Yulong, Zhang, Lingnan, Wang, Wenlong, Yu, Huanying
Publikováno v:
Journal of Dental Sciences; Oct2024, Vol. 19 Issue 4, p2268-2277, 10p
Publikováno v:
He jishu, Vol 46, Iss 7, Pp 070602-070602 (2023)
BackgroundThe metallic materials utilized for nuclear reactors undergo corosion due to the inherient high-temperature and high-pressure environment. Consequently, the corrosion products may be deposited in the core, called crud, and impact the fuel o
Externí odkaz:
https://doaj.org/article/8bfd380ee5594d8b873d26985f038d07
Publikováno v:
He jishu, Vol 46, Iss 3, Pp 030603-030603 (2023)
BackgroundUnder the condition of sub-cooled nucleate boiling (SNB), corrosion products in primary coolant of nuclear reactor will deposit on the outer surface of fuel cladding, which is commonly called fuel crud. Previous literature shown, zinc injec
Externí odkaz:
https://doaj.org/article/747ccc92cd1542338504c187621266bb