Zobrazeno 1 - 10
of 114
pro vyhledávání: '"Youqi Zheng"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3571-3584 (2024)
Reactor core transient calculation is very important for the reactor safety analysis, in which the kernel is neutron kinetics calculation by simulating the variation of neutron density or thermal power over time. Compared with the point kinetics meth
Externí odkaz:
https://doaj.org/article/03bd472632a14ad6bf45225a52241106
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2019-2028 (2024)
Advanced nuclear reactors, especially the newly developed small and micro-reactors have complex neutron spectrum, which makes the deterministic reactor core calculations sensitive to the energy group structure of few-group cross-sections. To avoid si
Externí odkaz:
https://doaj.org/article/d8166ecd9cb74fbfa3f5d19018a693a0
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 1116-1123 (2024)
–In recent years, unmanned underwater vehicles (UUV) have been vigorously developed, and with the continuous deepening of marine exploration, traditional energy can no longer meet the energy supply. Nuclear energy can achieve a huge and sustainable
Externí odkaz:
https://doaj.org/article/b87e00a7e68e41409ea0a6a445dd67e5
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4518-4526 (2023)
NECP-SARAX is a neutronics analysis code system for advanced reactor developed by Nuclear Engineering Computational Physics Laboratory of Xi'an Jiaotong University. In past few years, improvements have been implemented in TULIP code which is the cros
Externí odkaz:
https://doaj.org/article/462bc50675d44fd6914b6f8a8a502c91
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 5, Pp 1813-1824 (2022)
This paper shows the verification work of SARAX code system in the reactor core transient calculation based on the simplified EBR-II Benchmark. The SARAX code system is an analysis package developed by Xi'an Jiaotong University and aims at the advanc
Externí odkaz:
https://doaj.org/article/221b0f6a67874670ae4deda2d99d2bdd
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
Coarse-mesh finite difference (CMFD) method is a widely used numerical acceleration method. However, the stability of CMFD method is not good for the problems with optically thick regions. In this paper, a stability rule named the “sign preservatio
Externí odkaz:
https://doaj.org/article/af66c44dd62f45bca70c2ba86ae1946d
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 732-740 (2021)
Scattering resonance of medium mass nuclides leads complex spectrum in the fast reactor, which requires thousands of energy groups in the spectrum calculation. When the broad-group cross sections are collapsed, reaction rate cannot be completely cons
Externí odkaz:
https://doaj.org/article/7f028b6b26b34814a7c63ec6c78e7b7d
Autor:
Youqi Zheng, Chunhong Yang
Publikováno v:
Frontiers in Psychology, Vol 11 (2020)
Externí odkaz:
https://doaj.org/article/f60383dd1ebd42e9afcf19e0c4db7d83
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 8, Pp 1600-1609 (2017)
The accelerator-driven subcritical system (ADS) is driven by a neutron source from spallation reactions introduced by the injected proton beam. Part of the neutron source has energy as high as a few hundred MeV to a few GeV. The effects of high-energ
Externí odkaz:
https://doaj.org/article/c9a6917fff864ae2ae7c8860fdeba611
Publikováno v:
Energies, Vol 14, Iss 13, p 4042 (2021)
Among all the possible occurring reactivity effects of a fast reactor, the situations whereby the control rod was inserted, or the coolant was voided could lead to strong anisotropy of neutron flux distribution, therefore the angular dependence on ne
Externí odkaz:
https://doaj.org/article/8ab20c0f6e2c47ebaca2479b984a217e