Zobrazeno 1 - 10
of 21
pro vyhledávání: '"Sicong Xiao"'
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
A steady state model of the NuScale reactor has been built using the thermal hydraulic module CESAR of the severe accident code ASTEC. Construction of the model was achieved through iterations based on convergence towards data provided by NuScale per
Externí odkaz:
https://doaj.org/article/219a94e03840473fadefb66f8067fa9e
Publikováno v:
ASCE-ASME Journal of Risk & Uncertainty in Engineering Systems, Part A: Civil Engineering; Jun2024, Vol. 10 Issue 2, p1-20, 20p
Autor:
Yimeng Chan, Sicong Xiao
Publikováno v:
Nuclear Science and Engineering. 194:554-571
The recently developed linear prolongation Coarse Mesh Finite Difference (lpCMFD) acceleration scheme, which employs a linear additive approach to update the scalar flux, has been shown to be more ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b483200da77b86139570a14b6d407e23
https://doi.org/10.1080/00295639.2020.1752045
https://doi.org/10.1080/00295639.2020.1752045
Autor:
Yimeng Chan, Sicong Xiao
Publikováno v:
Annals of Nuclear Energy. 134:273-283
Previous works have derived the Fourier analysis for different CMFD based neutron transport acceleration schemes for 1D problems to study the convergence performance, in which the recently developed lpCMFD scheme gives best convergence performance du
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::66be61f8af7c6b47423ab654209a9f6a
https://doi.org/10.1016/j.anucene.2019.06.021
https://doi.org/10.1016/j.anucene.2019.06.021
Autor:
Yimeng Chan, Sicong Xiao
Publikováno v:
Annals of Nuclear Energy. 133:327-337
The recently developed lpCMFD scheme has been shown to be unconditionally stable and more effective than CMFD scheme for 2D fixed source neutron transport problems by using Fourier analysis. Previous works have derived the Fourier analysis to study t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::efb6c4f80b0b7cb2017090e6d55174f4
https://doi.org/10.1016/j.anucene.2019.05.035
https://doi.org/10.1016/j.anucene.2019.05.035
Publikováno v:
Nuclear Science and Engineering. 192:208-217
We present a local adaptive diffusion synthetic acceleration (DSA) method for neutron transport calculations. This new DSA method, called DG-DSA, solves the diffusion equation on a coarse mesh usin...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::26589fef8bf9cf527692a6fd2cf9dc94
https://doi.org/10.1080/00295639.2018.1499338
https://doi.org/10.1080/00295639.2018.1499338
Autor:
Dean Wang, Sicong Xiao
Publikováno v:
Nuclear Science and Engineering. 190:45-55
In this paper, we propose a new prolongation method to replace the conventional flat flux ratio–based scaling approach of coarse-mesh finite difference (CMFD) for updating the flux. The new prolong...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a883a44c840fb9d6d7e2f6e201fa37e2
https://doi.org/10.1080/00295639.2017.1417347
https://doi.org/10.1080/00295639.2017.1417347
Publikováno v:
Annals of Nuclear Energy. 112:666-672
In this paper, an integrated fusion-fission hybrid reactor energy system aiming at utilizing the thorium fuel efficiently with Th-U closed cycle is presented. The ultimate purpose is transition to the all thorium fueled energy system with the bred 23
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dfa92841bf5b9b357823bab6bce5acf0
https://doi.org/10.1016/j.anucene.2017.11.001
https://doi.org/10.1016/j.anucene.2017.11.001
Autor:
Yimeng Chan, Sicong Xiao
Publikováno v:
Annals of Nuclear Energy. 163:108562
In this paper, the linear prolongation CMFD acceleration scheme is extended for Monte Carlo k-eigenvalue neutron transport problems by adopting a modified weight adjustment method, where the weight-adjustment is performed on the fine mesh basis inste
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a690ea7f560acf6d54ea218528c7d021
https://doi.org/10.1016/j.anucene.2021.108562
https://doi.org/10.1016/j.anucene.2021.108562
Publikováno v:
Fusion Science and Technology. 73:559-567
In this technical note, an innovative thorium-uranium–fueled fusion-fission hybrid reactor (FFHR) design that employs a dual-coolant system to enhance 233U breeding and is based on a three-dimensional engineering model is presented. The reactor con
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::71b3905d32fd50a40c3ea0ed3ccc467e
https://doi.org/10.1080/15361055.2017.1396113
https://doi.org/10.1080/15361055.2017.1396113