Zobrazeno 1 - 10
of 95
pro vyhledávání: '"Du Xianan"'
Publikováno v:
He jishu, Vol 46, Iss 12, Pp 120604-120604 (2023)
BackgroundNECP-SARAX is a neutronics analysis code system for advanced reactors developed by the Nuclear Engineering Computational Physics Laboratory team of Xi'an Jiaotong University. In the past few years, a considerable amount of verification and
Externí odkaz:
https://doaj.org/article/9db2a9807efb4dfeb4922e4da4d8e54a
Publikováno v:
He jishu, Vol 46, Iss 2, Pp 020606-020606 (2023)
BackgroundAccording to the requirements of unmanned underwater vehicles for high reliability, high power, and long-life power, the design scheme of the megawatt heat pipe nuclear reactor silent unmanned portable reactor (UPR-s) is proposed by Xi'an J
Externí odkaz:
https://doaj.org/article/35eb7faae0bb4be098a0ed50444cbed1
Autor:
YIN Huabei, WANG Yongping, GOU Junli, LIU Guoming, ZU Tiejun, YIN Wen, ZHENG Youqi, DU Xianan
Publikováno v:
He jishu, Vol 46, Iss 1, Pp 010601-010601 (2023)
BackgroundNuclear critical safety analysis is the key technology to ensure the safety of spent fuel reprocessing plant. However, the present critical safety analysis codes for solution system are either limited in the geometric scope of application,
Externí odkaz:
https://doaj.org/article/a295fd7b5a33473aa496018f7a3524f6
Publikováno v:
He jishu, Vol 45, Iss 10, Pp 100601-100601 (2022)
BackgroundAt present, in the key stage of the construction of China Initiative Accelerator Driven System, various research institutes have also put forward corresponding core schemes for different purposes, including the accelerators drive advanced n
Externí odkaz:
https://doaj.org/article/b0957bdfe9414c359cbabf16beda671a
Publikováno v:
EPJ Web of Conferences, Vol 247, p 02007 (2021)
Recent researches have become more interested in the feasibility of using Monte Carlo (MC) code to generate multi-group (MG) cross sections (XSs) for fast reactor analysis using nodal diffusion codes. The current study, therefore, presents a brief me
Externí odkaz:
https://doaj.org/article/3a1bf27d25934f9a852acb2a7a2a7375
Publikováno v:
EPJ Web of Conferences, Vol 247, p 07009 (2021)
Decay heat (DH) is the heat produced through a radioactive decay of fission products during or after a reactor operation. It is known as the second largest source of power in the core after fission. Being such a strong contributor to reactor power, i
Externí odkaz:
https://doaj.org/article/1c670d36623845fd82e8d531090071f4
Publikováno v:
In Nuclear Engineering and Technology September 2024 56(9):3571-3584
Publikováno v:
In Annals of Nuclear Energy February 2025 211
Publikováno v:
In Nuclear Engineering and Technology June 2024 56(6):2019-2028
Autor:
Wu, Yunqin, Zheng, Youqi, Chen, Qichang, Li, Jinming, Du, Xianan, Wang, Yongping, Tao, Yushan
Publikováno v:
In Nuclear Engineering and Technology March 2024 56(3):1116-1123